subject:(radiation detection)

Kansas State University

1. George, Tyrel Daniel Frank. Design and testing of long-lifetime active sensor arrays for in-core multi-dimensional flux measurements.

Degree: MS, Department of Mechanical and Nuclear Engineering, 2016, Kansas State University

URL: http://hdl.handle.net/2097/35229

► Fission chambers are a common type of detector used to determine the neutron flux and power of a nuclear reactor. Due to the limited space… (more)

▼ Fission chambers are a common type of detector used to determine the neutron flux and power of a nuclear reactor. Due to the limited space and high neutron flux in a reactor core, it is difficult to perform real-time flux measurements with present-day in-core instrumentation. Micro-pocket fission detectors, or MPFDs, are relatively small in size and have low neutron sensitivity while retaining a large neutron to gamma ray discrimination ratio, thereby, allowing them to be used as active neutron flux monitors inside a nuclear reactor core. The micro-pocket fission chamber allows for multiple detectors to be inserted into a flux port or other available openings within the nuclear reactor core. Any material used to construct the MPFD must be rugged and capable of sustaining radiation damage for long periods of time. Each calibrated MPFD provides measurements of the flux for a discrete location. The size of these detectors allows for a spatial map of the flux to be developed, enabling real-time analysis of core burnup, power peaking, and rod shadowing. Small diameter thermocouples can be included with the array to also measure the temperature at each location. The following document details the research and development of MPFDs for long term use in nuclear power reactors. Previous MPFD designs were improved, miniaturized, and optimized for long term operations in reactor test ports designed for passive measurements of fluence using iron wires. Detector chambers with dimensions of 0.08 in x 0.06 in x 0.04 in were attached to a common cathode and individual anodes to construct an array of the MPFDs. Each array was tested at the Kansas State University TRIGA Mark II nuclear reactor to demonstrate functionality. The linear response in reactor power was measured. These arrays have also demonstrated reactor power tracking by following reactivity changes in steady state operations and reactor pulsing events. Stability testing showed consistent operation at 100 kW for several hours. The MPFDs have been demonstrated to be a viable technology for in-core measurements. Advisors/Committee Members: Douglas S. McGregor.

Subjects/Keywords: Radiation detection; Neutron detection

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APA (6^th Edition):

George, T. D. F. (2016). Design and testing of long-lifetime active sensor arrays for in-core multi-dimensional flux measurements. (Masters Thesis). Kansas State University. Retrieved from http://hdl.handle.net/2097/35229

Chicago Manual of Style (16^th Edition):

George, Tyrel Daniel Frank. “Design and testing of long-lifetime active sensor arrays for in-core multi-dimensional flux measurements.” 2016. Masters Thesis, Kansas State University. Accessed March 01, 2021. http://hdl.handle.net/2097/35229.

MLA Handbook (7^th Edition):

George, Tyrel Daniel Frank. “Design and testing of long-lifetime active sensor arrays for in-core multi-dimensional flux measurements.” 2016. Web. 01 Mar 2021.

Vancouver:

George TDF. Design and testing of long-lifetime active sensor arrays for in-core multi-dimensional flux measurements. [Internet] [Masters thesis]. Kansas State University; 2016. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2097/35229.

Council of Science Editors:

George TDF. Design and testing of long-lifetime active sensor arrays for in-core multi-dimensional flux measurements. [Masters Thesis]. Kansas State University; 2016. Available from: http://hdl.handle.net/2097/35229

Penn State University

2. Mcgahee, Christopher Oliver. HIGH EFFICIENCY FAST NEUTRON DETECTION SYSTEM.

Degree: 2017, Penn State University

URL: https://submit-etda.libraries.psu.edu/catalog/14460cfm5250

► There has been a call over the past decade to create a replacement neutron detection technology for He gas proportional systems1. Following a drastic increase… (more)

Subjects/Keywords: Neutron; Radiation Detection; Safeguards; Nonproliferation

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APA (6^th Edition):

Mcgahee, C. O. (2017). HIGH EFFICIENCY FAST NEUTRON DETECTION SYSTEM. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/14460cfm5250

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Mcgahee, Christopher Oliver. “HIGH EFFICIENCY FAST NEUTRON DETECTION SYSTEM.” 2017. Thesis, Penn State University. Accessed March 01, 2021. https://submit-etda.libraries.psu.edu/catalog/14460cfm5250.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Mcgahee, Christopher Oliver. “HIGH EFFICIENCY FAST NEUTRON DETECTION SYSTEM.” 2017. Web. 01 Mar 2021.

Vancouver:

Mcgahee CO. HIGH EFFICIENCY FAST NEUTRON DETECTION SYSTEM. [Internet] [Thesis]. Penn State University; 2017. [cited 2021 Mar 01]. Available from: https://submit-etda.libraries.psu.edu/catalog/14460cfm5250.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Mcgahee CO. HIGH EFFICIENCY FAST NEUTRON DETECTION SYSTEM. [Thesis]. Penn State University; 2017. Available from: https://submit-etda.libraries.psu.edu/catalog/14460cfm5250

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of Tennessee – Knoxville

3. Comer, Eleanor Paige. Improving the Scintillation Performance of KSr2I5:Ce3+ through Exploration of Activator Concentration and Growth Conditions.

Degree: MS, Nuclear Engineering, 2019, University of Tennessee – Knoxville

URL: https://trace.tennessee.edu/utk_gradthes/5414

► Potassium strontium iodide (KSr₂I₅ or KSI) has been previously discovered and investigated as a high energy resolution scintillator for national security applications. Activators were investigated… (more)

Subjects/Keywords: scintillator; radiation detection; nuclear security

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APA (6^th Edition):

Comer, E. P. (2019). Improving the Scintillation Performance of KSr2I5:Ce3+ through Exploration of Activator Concentration and Growth Conditions. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/5414

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Comer, Eleanor Paige. “Improving the Scintillation Performance of KSr2I5:Ce3+ through Exploration of Activator Concentration and Growth Conditions.” 2019. Thesis, University of Tennessee – Knoxville. Accessed March 01, 2021. https://trace.tennessee.edu/utk_gradthes/5414.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Comer, Eleanor Paige. “Improving the Scintillation Performance of KSr2I5:Ce3+ through Exploration of Activator Concentration and Growth Conditions.” 2019. Web. 01 Mar 2021.

Vancouver:

Comer EP. Improving the Scintillation Performance of KSr2I5:Ce3+ through Exploration of Activator Concentration and Growth Conditions. [Internet] [Thesis]. University of Tennessee – Knoxville; 2019. [cited 2021 Mar 01]. Available from: https://trace.tennessee.edu/utk_gradthes/5414.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Comer EP. Improving the Scintillation Performance of KSr2I5:Ce3+ through Exploration of Activator Concentration and Growth Conditions. [Thesis]. University of Tennessee – Knoxville; 2019. Available from: https://trace.tennessee.edu/utk_gradthes/5414

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Penn State University

4. Wart, Megan Frances. Evaluation of the Experimental Set-up for Lead Zirconate Titanate Irradiation with Fission Fragments.

Degree: 2017, Penn State University

URL: https://submit-etda.libraries.psu.edu/catalog/14341mvw5502

► Piezoelectric materials convert mechanical to electrical energy, due to dipoles in their crystal structure. This characteristic may allow for piezoelectric materials to be used to… (more)

▼ Piezoelectric materials convert mechanical to electrical energy, due to dipoles in their crystal structure. This characteristic may allow for piezoelectric materials to be used to detect radiation. As radiation bombards the material it stresses the crystalline structure and, if there is sufficient stress, an electrical signal will be produced. To determine if this proposed method of radiation detection would work, the threshold of radiation exposure required to create an electrical signal must be determined. To enable such experiments, an experimental set up must be designed and evaluated computationally for radiation safety and feasibility. This includes choosing a form of radiation and the source to provide it, as well as determining how the piezoelectric plates will be prepared. For these experiments, fission fragments will be used due to there relatively high mass, high energy, high specific ionization, and short range. To produce them, a highly enriched uranium foil will be irradiated with a neutron source. A frame was built to hold this foil securely against the samples of piezoelectric material. Lead zirconate titanate was chosen as the piezoelectric material to be tested since it is relatively inexpensive and commercially available. To determine the feasibility of the experiments and the appropriate source, the fission rate and fission fragment production were calculated using a Monte Carlo code for each of the two available sources: a plutonium beryllium source, and the thermal neutron beamline at the Breazeale reactor. Using the fission rate and the range a fission fragment of average mass, the flux of fission fragments entering the piezoelectric plates was calculated. Through this calculation it was shown that the thermal neutron beamline would provide the larger fission fragment flux to the samples. To maximize the fission fragment flux, in order to improve the chances of seeing an electrical signal, it was concluded that the thermal neutron beamline should be used. In the future, other types of radiation, such as alphas or neutrons will be tested. The piezoelectric material will also be optimized, by choosing a different compound, structure, or creating custom piezoelectric materials. Advisors/Committee Members: Marek Flaska, Thesis Advisor/Co-Advisor.

Subjects/Keywords: radiation detection; fission fragment detection; piezoelectric materials

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APA (6^th Edition):

Wart, M. F. (2017). Evaluation of the Experimental Set-up for Lead Zirconate Titanate Irradiation with Fission Fragments. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/14341mvw5502

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Wart, Megan Frances. “Evaluation of the Experimental Set-up for Lead Zirconate Titanate Irradiation with Fission Fragments.” 2017. Thesis, Penn State University. Accessed March 01, 2021. https://submit-etda.libraries.psu.edu/catalog/14341mvw5502.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Wart, Megan Frances. “Evaluation of the Experimental Set-up for Lead Zirconate Titanate Irradiation with Fission Fragments.” 2017. Web. 01 Mar 2021.

Vancouver:

Wart MF. Evaluation of the Experimental Set-up for Lead Zirconate Titanate Irradiation with Fission Fragments. [Internet] [Thesis]. Penn State University; 2017. [cited 2021 Mar 01]. Available from: https://submit-etda.libraries.psu.edu/catalog/14341mvw5502.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Wart MF. Evaluation of the Experimental Set-up for Lead Zirconate Titanate Irradiation with Fission Fragments. [Thesis]. Penn State University; 2017. Available from: https://submit-etda.libraries.psu.edu/catalog/14341mvw5502

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Penn State University

5. Duffin, Taylor Gregory. Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology.

Degree: 2017, Penn State University

URL: https://submit-etda.libraries.psu.edu/catalog/14416tbd5106

► The threat of nuclear proliferation and nuclear terrorism are strong motivators for systems that can detect special nuclear materials, including those that are heavily shielded… (more)

Subjects/Keywords: Radiation Detection; Drones; Neutron Detection; Searching Methods

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APA (6^th Edition):

Duffin, T. G. (2017). Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/14416tbd5106

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Duffin, Taylor Gregory. “Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology.” 2017. Thesis, Penn State University. Accessed March 01, 2021. https://submit-etda.libraries.psu.edu/catalog/14416tbd5106.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Duffin, Taylor Gregory. “Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology.” 2017. Web. 01 Mar 2021.

Vancouver:

Duffin TG. Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology. [Internet] [Thesis]. Penn State University; 2017. [cited 2021 Mar 01]. Available from: https://submit-etda.libraries.psu.edu/catalog/14416tbd5106.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Duffin TG. Localization of Neutron Sources with Mobile Radiation Detectors Based on Drone Technology. [Thesis]. Penn State University; 2017. Available from: https://submit-etda.libraries.psu.edu/catalog/14416tbd5106

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Colorado State University

6. Mann, Jenelle. Improved detection of radioactive material using a series of measurements.

Degree: PhD, Environmental and Radiological Health Sciences, 2016, Colorado State University

URL: http://hdl.handle.net/10217/176788

► The goal of this project is to develop improved algorithms for detection of radioactive sources that have low signal compared to background. The detection of… (more)

Subjects/Keywords: instrumentation; statistics; radiation detection; detection statistics

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APA (6^th Edition):

Mann, J. (2016). Improved detection of radioactive material using a series of measurements. (Doctoral Dissertation). Colorado State University. Retrieved from http://hdl.handle.net/10217/176788

Chicago Manual of Style (16^th Edition):

Mann, Jenelle. “Improved detection of radioactive material using a series of measurements.” 2016. Doctoral Dissertation, Colorado State University. Accessed March 01, 2021. http://hdl.handle.net/10217/176788.

MLA Handbook (7^th Edition):

Mann, Jenelle. “Improved detection of radioactive material using a series of measurements.” 2016. Web. 01 Mar 2021.

Vancouver:

Mann J. Improved detection of radioactive material using a series of measurements. [Internet] [Doctoral dissertation]. Colorado State University; 2016. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/10217/176788.

Council of Science Editors:

Mann J. Improved detection of radioactive material using a series of measurements. [Doctoral Dissertation]. Colorado State University; 2016. Available from: http://hdl.handle.net/10217/176788

Texas A&M University

7. Shah, Manit Devendrabhai. Radiation Detection using Integrated Circuits.

Degree: PhD, Nuclear Engineering, 2016, Texas A&M University

URL: http://hdl.handle.net/1969.1/174255

► The research objective of this dissertation is to evaluate the capability of ‘radiation’ integrated circuits (RICs) to serve as a new type of radiation detection… (more)

▼ The research objective of this dissertation is to evaluate the capability of ‘radiation’ integrated circuits (RICs) to serve as a new type of radiation detection medium. Designed at Texas A&M University, the RIC contains both radiation-sensitive areas (RSAs) and radiation-hardened areas (RHAs). RSAs are designed so that their electrical properties change when exposed to charged particles. RHAs monitor such changes in RSAs to detect the presence of radiation. Novel detector designs utilizing the RICs were assessed and optimized, using both analytical and simulation methods, to register the major types of radiation: alpha particles, beta particles, gamma rays, and neutrons. The detector system materials and components were varied to characterize different configurations and recommend optimized RIC detector designs. The proposed revolutionary RIC-alpha/beta probe design has two regions: one to detect alpha particles and another to detect betas along with their Eβmax (maximum beta-particle energy). In order to perform the Eβmax discrimination, the maximum penetration depth property of betas in the attenuator was utilized. In MCNPX, plate glass, Pyrex® glass, Lucite®, and natural rubber were studied as attenuator materials. For the proof of concept, attenuator materials in the shape of a wedge were analyzed. The natural rubber in the form of a wedged attenuator was observed to show superior Eβmax discrimination compared to other defined attenuators. The Eβmax resolution capability of 50-keV is possible using natural rubber attenuator. The proposed RIC-neutron detector design uses enriched boron (96% 10^B) as a neutron-reactive coating to generate secondary charged particles. In MCNPX, other neutron-reactive materials (natural boron, B4C, and LiF) were also studied. Analysis showed that compared to other charged particles, alpha-particles were the major contributor to the signal generation in RSAs designed to detect neutrons. With the optimal thickness of 3-µm enriched boron, the signal to noise ratio for thermal neutron detection was increased by approximately three orders of magnitude. The proposed RIC-gamma ray detection system uses a sodium iodide crystal, photocathodes, and the RIC. Unlike the traditional design, the proposed approach places photocathodes on all crystal surfaces to collect optical photons and generate photoelectrons. These photoelectrons interact to generate an electrical signal in the RSAs, and thereby the RIC detects gamma rays. The collection ratio (i.e., the number of collected optical photons under the proposed design compared to the number using a traditional design) was found to be a function of the crystal size, gamma-ray energy, and the source position. The concentration of photoelectrons as a function of the RSA radius size was also assessed to optimize the RSA size. Advisors/Committee Members: Marianno, Craig M (advisor), Khatri, Sunil P (committee member), Boyle, David R (committee member), Poston, Sr., John W (committee member).

Subjects/Keywords: radiation detection; alpha; beta; gamma; neutron; RIC

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Shah, M. D. (2016). Radiation Detection using Integrated Circuits. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/174255

Chicago Manual of Style (16^th Edition):

Shah, Manit Devendrabhai. “Radiation Detection using Integrated Circuits.” 2016. Doctoral Dissertation, Texas A&M University. Accessed March 01, 2021. http://hdl.handle.net/1969.1/174255.

MLA Handbook (7^th Edition):

Shah, Manit Devendrabhai. “Radiation Detection using Integrated Circuits.” 2016. Web. 01 Mar 2021.

Vancouver:

Shah MD. Radiation Detection using Integrated Circuits. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/1969.1/174255.

Council of Science Editors:

Shah MD. Radiation Detection using Integrated Circuits. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/174255

Penn State University

8. Sarnoski, Sarah Elizabeth. Validation of Performance Measurements of The Penn State Compton Suppression System.

Degree: 2016, Penn State University

URL: https://submit-etda.libraries.psu.edu/catalog/28877

► Compton suppression is a measurement technique that reduces the intensity of the Compton continuum, which is composed of the partial energy depositions created via Compton… (more)

▼ Compton suppression is a measurement technique that reduces the intensity of the Compton continuum, which is composed of the partial energy depositions created via Compton scattering of gamma rays in the detector material. The Compton continuum from a high-energy gamma ray can obscure the full-energy gamma ray photopeaks of isotopes with lower energy gamma ray emissions. The reduction from the Compton suppression system enables a more accurate identification of these low-energy gamma rays with energy peaks located within the Compton continuum. The Penn State Compton suppression system (CSS) uses a high purity germanium (HPGe) detector and a cylindrical and plug sodium iodide (NaI(Tl)) guard detector to negate the effect of partially deposited gamma rays on the gamma spectrum produced when measuring a sample. The Penn State CSS negates the effect of partially deposited gamma rays on the overall gamma spectrum, therefore producing a more accurate spectrum with fewer overall counts and reduced background interference. The research performed in this thesis used the Penn State CSS to validate earlier sample measurements obtained prior to the dismantling and reconstruction of the CSS. The Penn State CSS has produced superior results when compared with published literature, and it is important that it continues to perform at this level after reconstruction. 137Cs, 60Co, and irradiated National Institute of Standards and Technology (NIST) standard reference materials were measured in the CSS. A suppression factor (SF) is a comparison of suppressed to unsuppressed peak to Compton ratios, a further explanation and definition is provided in section 6.3 of this thesis. The suppression factor (SF) for the 137Cs calibrated gamma ray spectrum was 9.21, similar to the previous SF measurement of 9.97. These values are approximately 28% larger than most SFs recorded in literature, demonstrating the superior ability of the Penn State CSS. Using the calibrated Penn State CSS, two NIST standard reference materials, SRM 1570 Spinach Leaves and SRM 1571 Orchard Leaves, were measured after irradiation in the Penn State Breazeale Reactor (PSBR). Bare and cadmium covered gold wires were also irradiated in the PSBR to characterize the neutron flux shape of the current core design of the reactor. Peak and average neutron fluxes were determined for each of the irradiation locations, and the axial positions where peak neutron fluxes occurred were determined. The reference materials were irradiated both in the PSBR dry tubes and using the PSBR pneumatic transfer system. The dry tube irradiation of SRM-1570 produced a SF of 3.30 and the pneumatic transfer irradiation of SRM-1570 produced a SF of 3.27±0.21; these values are functionally equivalent. The pneumatic transfer irradiation of SRM-1571 produced a suppression factor of 4.2±0.10, approximately 10% greater than a previous measurement of 3.80. This work irradiated and measured the standard reference materials in triplicate, providing a more accurate evaluation of the CSS capabilities than… Advisors/Committee Members: Kenan Unlu, Thesis Advisor/Co-Advisor.

Subjects/Keywords: Compton Suppression; Radiation Detection; Nuclear Engineering

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Sarnoski, S. E. (2016). Validation of Performance Measurements of The Penn State Compton Suppression System. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/28877

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Sarnoski, Sarah Elizabeth. “Validation of Performance Measurements of The Penn State Compton Suppression System.” 2016. Thesis, Penn State University. Accessed March 01, 2021. https://submit-etda.libraries.psu.edu/catalog/28877.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Sarnoski, Sarah Elizabeth. “Validation of Performance Measurements of The Penn State Compton Suppression System.” 2016. Web. 01 Mar 2021.

Vancouver:

Sarnoski SE. Validation of Performance Measurements of The Penn State Compton Suppression System. [Internet] [Thesis]. Penn State University; 2016. [cited 2021 Mar 01]. Available from: https://submit-etda.libraries.psu.edu/catalog/28877.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Sarnoski SE. Validation of Performance Measurements of The Penn State Compton Suppression System. [Thesis]. Penn State University; 2016. Available from: https://submit-etda.libraries.psu.edu/catalog/28877

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of Ontario Institute of Technology

9. Broughton, David. Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry.

Degree: 2016, University of Ontario Institute of Technology

URL: http://hdl.handle.net/10155/637

► Neutron dosimetry in reactor fields is currently conducted using thermal neutron flux monitors. It has been demonstrated that Tissue Equivalent Proportional Counters (TEPCs) have the… (more)

▼ Neutron dosimetry in reactor fields is currently conducted using thermal neutron flux monitors. It has been demonstrated that Tissue Equivalent Proportional Counters (TEPCs) have the potential to improve the accuracy of neutron dosimetry in these reactor fields, and Multi-Element Tissue Equivalent Proportional Counters (METEPCs) could reduce the size of instrumentation required to do so. The current METEPC designs are prohibitively complex and are sensitive to motion and audible noise. This work proposes a novel hemispherical element with a wire-less anode ball as a solution. The hemispherical METEPC element was analyzed as a single TEPC to first demonstrate the potential of this new design. Its performance was evaluated relative to current cylindrical and spherical counter designs that have been demonstrated experimentally to perform very well. The performance analysis first used equipotential distributions generated with ANSYS Maxwell (V. 14.0) in order to solve the Townsend equation and calculate radial gas gain distributions for each counter. Through this it was found that the hemispherical counter exhibits completely uniform gas gain for electrons approaching the anode from all directions and its avalanche region occupies only 0.0004% of the entire gas cavity volume, whereas in the cylindrical and spherical counters the avalanche occupies 0.6% and 0.12% of the total gas cavity volume, respectively. Energy deposition simulations were conducted using the Monte Carlo code PHITS (V. 2.24) with both mono-energetic 2.5 MeV neutrons and the neutron spectrum of 252Cf-D2O moderated. In these neutron fields the hemispherical counter appears to be a good alternative to the reference spherical geometry, whereas the cylindrical counter tends to under-respond to H*(10) for the lower neutron energies of the 252Cf-D2O moderated field. These theoretical results are promising, and if the recommended follow-up experimental work demonstrates the hemispherical counter works as anticipated it will be ready to be incorporated into an METEPC design. Advisors/Committee Members: Waker, Anthony.

Subjects/Keywords: Microdosimetry; TEPC; Neutron dosimetry; PHITS; Radiation detection

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APA (6^th Edition):

Broughton, D. (2016). Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/637

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Broughton, David. “Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry.” 2016. Thesis, University of Ontario Institute of Technology. Accessed March 01, 2021. http://hdl.handle.net/10155/637.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Broughton, David. “Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry.” 2016. Web. 01 Mar 2021.

Vancouver:

Broughton D. Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry. [Internet] [Thesis]. University of Ontario Institute of Technology; 2016. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/10155/637.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Broughton D. Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry. [Thesis]. University of Ontario Institute of Technology; 2016. Available from: http://hdl.handle.net/10155/637

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of California – Berkeley

10. Schuster, Patricia Frances. Investigating the Anisotropic Scintillation Response in Organic Crystal Scintillator Detectors.

Degree: Nuclear Engineering, 2016, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/81z4t4xs

► Organic scintillator materials have long been used as radiation detectors. They offer simultaneous detection of fast neutrons and gamma rays for applications in nuclear nonproliferation,… (more)

▼ Organic scintillator materials have long been used as radiation detectors. They offer simultaneous detection of fast neutrons and gamma rays for applications in nuclear nonproliferation, international safeguards, and national security. The recent development of high quality stilbene crystals with excellent neutron-gamma pulse shape discrimination (PSD) has generated renewed interest in using crystalline materials. However, crystal organic scintillators are subject to a directional dependence in their response to heavy charged particle interactions, degrading their energy resolution for neutron measurements and worsening their PSD performance. This dissertation presents several studies that experimentally characterize the scintillation anisotropy in organic crystal scintillators. These include measurements of neutron, gamma-ray and cosmic muon interactions in anthracene, a historical benchmark among organic scintillator materials, to confirm and extend measurements previously available in the literature. The gamma-ray and muon measurements provide new experimental confirmation that no scintillation anisotropy is present in their interactions. Observations from these measurements have updated the hypothesis for the physical mechanism that is responsible for the scintillation anisotropy concluding that a relatively high dE/dx is required in order to produce a scintillation anisotropy. The directional dependence of the scintillation output in liquid and plastic materials was measured to experimentally confirm that no scintillation anisotropy correlated to detector orientation exists in amorphous materials. These observations confirm that the scintillation anisotropy is not due to an external effect on the measurement system, and that a fixed, repeating structure is required for a scintillation anisotropy.The directional dependence of the scintillation output in response to neutron interactions was measured in four stilbene crystals of various sizes and growth-methods. The scintillation anisotropy in these materials was approximately uniform, indicating that the crystal size, geometry, and growth method do not significantly impact the effect. Measurements of three additional pure crystals and two mixed crystals were made. These measurements showed that 1) the magnitude of the effect varies with energy and material, 2) the relationship between the light output and pulse shape anisotropy varies across materials, and 3) the effect in mixed materials is very complex. These measurements have informed the hypothesis of the mechanism that produces the directional dependence. By comparing the various relationships between the light output and pulse shape anisotropy across materials, these measurements indicate that the preferred directions of singlet and triplet excitation transport may be the same in some materials and different in other materials. The measurements performed in this work serve as a resource to groups who aim to correct for the scintillation anisotropy or employ it as a directional detection modality.…

Subjects/Keywords: Nuclear engineering; Nuclear physics and radiation; neutron detection; organic scintillator; radiation detection; scintillation anisotropy

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APA (6^th Edition):

Schuster, P. F. (2016). Investigating the Anisotropic Scintillation Response in Organic Crystal Scintillator Detectors. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/81z4t4xs

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Schuster, Patricia Frances. “Investigating the Anisotropic Scintillation Response in Organic Crystal Scintillator Detectors.” 2016. Thesis, University of California – Berkeley. Accessed March 01, 2021. http://www.escholarship.org/uc/item/81z4t4xs.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Schuster, Patricia Frances. “Investigating the Anisotropic Scintillation Response in Organic Crystal Scintillator Detectors.” 2016. Web. 01 Mar 2021.

Vancouver:

Schuster PF. Investigating the Anisotropic Scintillation Response in Organic Crystal Scintillator Detectors. [Internet] [Thesis]. University of California – Berkeley; 2016. [cited 2021 Mar 01]. Available from: http://www.escholarship.org/uc/item/81z4t4xs.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Schuster PF. Investigating the Anisotropic Scintillation Response in Organic Crystal Scintillator Detectors. [Thesis]. University of California – Berkeley; 2016. Available from: http://www.escholarship.org/uc/item/81z4t4xs

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of Saskatchewan

11. Chicilo, Farley. Samarium-Doped Fluorophosphate and Fluoroaluminate Glasses for High-Dose High-Resolution Dosimetry for Microbeam Radiation Therapy.

Degree: 2020, University of Saskatchewan

URL: http://hdl.handle.net/10388/12847

► Microbeam Radiation Therapy (MRT) is an important and developing radiotherapy technique that uses spatially fractionated doses, several orders of magnitude larger than that of the… (more)

▼ Microbeam Radiation Therapy (MRT) is an important and developing radiotherapy technique that uses spatially fractionated doses, several orders of magnitude larger than that of the doses used in conventional radiation therapy. Healthy tissue displays remarkable resistance to damage caused from microscopically narrow, fractionated, planar beams of x-rays, while showing preferential damage towards cancerous growths, allowing for a high potential towards the treatment of often inoperable tumours. These synchrotron generated, spatially fractionated, planar beams are referred to as microbeams, and have a thickness of 20 – 50 µm and are separated by distances of 100 – 400 µm. The dose delivered at the center of the microbeam can be on the order of thousands of Grays (Gy), whereas the dose between each microbeam should be kept below tens of Gy. An important aspect of MRT is the spatial distribution of the dose delivered to the patient, which must be accurately measured. Ultimately, both high resolution and large dynamic range dosimetric measurements must be done simultaneously. The objective of this Ph.D. research involves the development and characterization of a dosimetric technique that fulfills the requirements of measuring dose distributions of microbeams. The proposed technique uses the indirect detection of x-rays, where the dose is recorded in a glass plate which can then be readout using a confocal microscopy system. The dose delivered is recorded by using trivalent samarium (Sm3+) doped fluoroaluminate and fluoro-phosphate glasses, where conversion from the trivalent form of samarium to the divalent form (Sm2+) occurs after exposure to x-rays. The extent of this conversion can be readout and digitized with high resolution using a confocal microscopy system that utilizes the easily distinguishable photoluminescent spectra of Sm3+ to Sm2+. The work carried out in this research involves the high resolution recording of microbeam profiles performed at the Canadian synchrotron, using samarium doped glass plates under a variety of irradiation parameters in order to determine their suitability for dosimetric applications. In particular, the dose rate and x-ray energy dependence of these materials is investigated, as well as the determination of the optimum Sm3+ dopant concentration. Further, the confocal measurement technique is investigated, as well as the suitability of ion implantation of samarium ions in order to improve the signal readout. Lastly, the change in dose distributions of microbeams is investigated by performing irradiations over a wide range of monochromatic x-rays, so that the potential effect of the selected energy on MRT treatment planning can be examined. Advisors/Committee Members: Kasap, Safa, Chapman, Dean, Chen, Daniel, Yang, Qiaoqin, Bradley, Michael, Chen, Li.

Subjects/Keywords: Microbeam Radiation Therapy; Dosimetry; Rare earth ions; Radiation detection

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APA (6^th Edition):

Chicilo, F. (2020). Samarium-Doped Fluorophosphate and Fluoroaluminate Glasses for High-Dose High-Resolution Dosimetry for Microbeam Radiation Therapy. (Thesis). University of Saskatchewan. Retrieved from http://hdl.handle.net/10388/12847

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Chicilo, Farley. “Samarium-Doped Fluorophosphate and Fluoroaluminate Glasses for High-Dose High-Resolution Dosimetry for Microbeam Radiation Therapy.” 2020. Thesis, University of Saskatchewan. Accessed March 01, 2021. http://hdl.handle.net/10388/12847.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Chicilo, Farley. “Samarium-Doped Fluorophosphate and Fluoroaluminate Glasses for High-Dose High-Resolution Dosimetry for Microbeam Radiation Therapy.” 2020. Web. 01 Mar 2021.

Vancouver:

Chicilo F. Samarium-Doped Fluorophosphate and Fluoroaluminate Glasses for High-Dose High-Resolution Dosimetry for Microbeam Radiation Therapy. [Internet] [Thesis]. University of Saskatchewan; 2020. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/10388/12847.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Chicilo F. Samarium-Doped Fluorophosphate and Fluoroaluminate Glasses for High-Dose High-Resolution Dosimetry for Microbeam Radiation Therapy. [Thesis]. University of Saskatchewan; 2020. Available from: http://hdl.handle.net/10388/12847

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of South Florida

12. Tichacek, Christopher John. Development of a Voxel-Based Monte Carlo Radiation Dosimetry Methodology for a Targeted Alpha Particle Therapy.

Degree: 2019, University of South Florida

URL: https://scholarcommons.usf.edu/etd/8081

► The use of targeted ligands to deliver radioisotopes directly to tumor cells is a promising therapeutic strategy. Because of the short path length and high… (more)

▼ The use of targeted ligands to deliver radioisotopes directly to tumor cells is a promising therapeutic strategy. Because of the short path length and high LET of alpha particles, targeted alpha particles are ideal for treating metastatic disease while minimizing damage to non-targeted tissues. However, clinical methods for determining 3D radiation dosimetry in patients with multiple metastatic lesions are needed to support clinical translation of novel targeted alpha particle therapies for personalized treatment, especially in patients that have previously received radiotherapy. Recently interest in novel radiopharmaceutical development has grown significantly. However, compared to external beam radiation therapy, progress in customizing radiopharmaceutical treatments specific to the patient has remained stagnant for decades. Currently, therapies are given using fixed dose administrations and dosimetry is performed using outdated simplistic representations of a standard human. The potential benefits of targeted alpha therapies cannot be taken advantage of until pretreatment planning is employed to optimize each patient’s therapy on an individual basis. Dose response relationships need to be analyzed post-treatment to assess tumor control probabilities and normal tissue complications. With new developments in medical imaging and instrumentation, along with the continuously increasing computational power available, personalized targeted alpha therapies can be achieved. In this work, a novel targeted alpha therapy for treatment of metastatic uveal melanoma, 225Ac-DOTA-MC1RL, is developed and thoroughly tested pre-clinically. The therapy showed rapid eradication of tumors with no normal tissue toxicity with a single administration. Radiation detection instrumentation is improved upon by developing a method to more accurately quantify radioactivity for administration, biodistribution, pharmacokinetics, and dosimetry. A voxel-based Monte Carlo dosimetry methodology is developed using a novel companion imaging agent in both phantom and in vivo pre-clinical imaging studies. From these studies, a clinically translatable workflow is described and tested. 3D dosimetry calculations were performed enabling volumetric dose analysis for the novel therapy.

Subjects/Keywords: Monte Carlo; Radiation Detection; Radiation Dosimetry; radiopharmaceutical therapy; Other Education

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APA (6^th Edition):

Tichacek, C. J. (2019). Development of a Voxel-Based Monte Carlo Radiation Dosimetry Methodology for a Targeted Alpha Particle Therapy. (Thesis). University of South Florida. Retrieved from https://scholarcommons.usf.edu/etd/8081

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Tichacek, Christopher John. “Development of a Voxel-Based Monte Carlo Radiation Dosimetry Methodology for a Targeted Alpha Particle Therapy.” 2019. Thesis, University of South Florida. Accessed March 01, 2021. https://scholarcommons.usf.edu/etd/8081.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Tichacek, Christopher John. “Development of a Voxel-Based Monte Carlo Radiation Dosimetry Methodology for a Targeted Alpha Particle Therapy.” 2019. Web. 01 Mar 2021.

Vancouver:

Tichacek CJ. Development of a Voxel-Based Monte Carlo Radiation Dosimetry Methodology for a Targeted Alpha Particle Therapy. [Internet] [Thesis]. University of South Florida; 2019. [cited 2021 Mar 01]. Available from: https://scholarcommons.usf.edu/etd/8081.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Tichacek CJ. Development of a Voxel-Based Monte Carlo Radiation Dosimetry Methodology for a Targeted Alpha Particle Therapy. [Thesis]. University of South Florida; 2019. Available from: https://scholarcommons.usf.edu/etd/8081

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Brno University of Technology

13. Lázna, Tomáš. Měření záření gama: Gamma Radiation Measurement.

Degree: 2019, Brno University of Technology

URL: http://hdl.handle.net/11012/39234

► This thesis is focused on detection of ionizing radiation, especially gamma radiation. In its theoretical part the issue is presented and the most common detector… (more)

Subjects/Keywords: radiace; záření gama; mobilní robot; dálková detekce; radiation; gamma radiation; mobile robot; remote detection

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APA (6^th Edition):

Lázna, T. (2019). Měření záření gama: Gamma Radiation Measurement. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/39234

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Lázna, Tomáš. “Měření záření gama: Gamma Radiation Measurement.” 2019. Thesis, Brno University of Technology. Accessed March 01, 2021. http://hdl.handle.net/11012/39234.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Lázna, Tomáš. “Měření záření gama: Gamma Radiation Measurement.” 2019. Web. 01 Mar 2021.

Vancouver:

Lázna T. Měření záření gama: Gamma Radiation Measurement. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/11012/39234.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Lázna T. Měření záření gama: Gamma Radiation Measurement. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/39234

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of Texas – Austin

14. Goshev, Stefan Antoanov. Analysis of smuggler movement on multiple transportation networks.

Degree: MSin Engineering, Operations Research and Industrial Engineering, 2011, University of Texas – Austin

URL: http://hdl.handle.net/2152/ETD-UT-2011-05-3357

► We analyze an interdiction problem in which a nuclear-material smuggler can traverse multiple transportation networks, wherein each edge has an indigenous probability of evasion. Our… (more)

Subjects/Keywords: Interdiction networks; Nuclear smuggling; Radiation detectors; Radiation warning systems; Detection; Nuclear counters

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APA (6^th Edition):

Goshev, S. A. (2011). Analysis of smuggler movement on multiple transportation networks. (Masters Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/ETD-UT-2011-05-3357

Chicago Manual of Style (16^th Edition):

Goshev, Stefan Antoanov. “Analysis of smuggler movement on multiple transportation networks.” 2011. Masters Thesis, University of Texas – Austin. Accessed March 01, 2021. http://hdl.handle.net/2152/ETD-UT-2011-05-3357.

MLA Handbook (7^th Edition):

Goshev, Stefan Antoanov. “Analysis of smuggler movement on multiple transportation networks.” 2011. Web. 01 Mar 2021.

Vancouver:

Goshev SA. Analysis of smuggler movement on multiple transportation networks. [Internet] [Masters thesis]. University of Texas – Austin; 2011. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2152/ETD-UT-2011-05-3357.

Council of Science Editors:

Goshev SA. Analysis of smuggler movement on multiple transportation networks. [Masters Thesis]. University of Texas – Austin; 2011. Available from: http://hdl.handle.net/2152/ETD-UT-2011-05-3357

University of Texas – Austin

15. Hawley, Megan Lynn. Interdicting smuggler movement with transparent and non-transparent assets.

Degree: MSin Engineering, Operations Research and Industrial Engineering, 2012, University of Texas – Austin

URL: http://hdl.handle.net/2152/ETD-UT-2012-05-5765

► We analyze an interdiction problem in which a nuclear-material smuggler can traverse the rail and road ports of entry (POEs) along the Mexican and Canadian… (more)

Subjects/Keywords: Interdiction networks; Nuclear smuggling; Radiation detectors; Radiation warning systems; Detection; Transparent assets; Non-transparent assets

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APA (6^th Edition):

Hawley, M. L. (2012). Interdicting smuggler movement with transparent and non-transparent assets. (Masters Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/ETD-UT-2012-05-5765

Chicago Manual of Style (16^th Edition):

Hawley, Megan Lynn. “Interdicting smuggler movement with transparent and non-transparent assets.” 2012. Masters Thesis, University of Texas – Austin. Accessed March 01, 2021. http://hdl.handle.net/2152/ETD-UT-2012-05-5765.

MLA Handbook (7^th Edition):

Hawley, Megan Lynn. “Interdicting smuggler movement with transparent and non-transparent assets.” 2012. Web. 01 Mar 2021.

Vancouver:

Hawley ML. Interdicting smuggler movement with transparent and non-transparent assets. [Internet] [Masters thesis]. University of Texas – Austin; 2012. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2152/ETD-UT-2012-05-5765.

Council of Science Editors:

Hawley ML. Interdicting smuggler movement with transparent and non-transparent assets. [Masters Thesis]. University of Texas – Austin; 2012. Available from: http://hdl.handle.net/2152/ETD-UT-2012-05-5765

16. Fronk, Ryan G. Dual-side etched microstructured semiconductor neutron detectors.

Degree: PhD, Department of Mechanical and Nuclear Engineering, 2017, Kansas State University

URL: http://hdl.handle.net/2097/35426

► Interest in high-efficiency replacements for thin-film-coated thermal neutron detectors led to the development of single-sided microstructured semiconductor neutron detectors (MSNDs). MSNDs are designed with micro-sized… (more)

▼ Interest in high-efficiency replacements for thin-film-coated thermal neutron detectors led to the development of single-sided microstructured semiconductor neutron detectors (MSNDs). MSNDs are designed with micro-sized trench structures that are etched into a vertically-oriented pvn-junction diode, and backfilled with a neutron converting material, such as ⁶LiF. Neutrons absorbed by the converting material produce a pair of charged-particle reaction products that can be measured by the diode substrate. MSNDs have higher neutron-absorption and reaction-product counting efficiencies than their thin-film-coated counterparts, resulting in up to a 10x increase in intrinsic thermal neutron detection efficiency. The detection efficiency for a single-sided MSND is reduced by neutron streaming paths between the conversion-material filled regions that consequently allow neutrons to pass undetected through the detector. Previously, the highest reported intrinsic thermal neutron detection efficiency for a single MSND was approximately 30%. Methods for double-stacking and aligning MSNDs to reduce neutron streaming produced devices with an intrinsic thermal neutron detection efficiency of 42%. Presented here is a new type of MSND that features a complementary second set of trenches that are etched into the back-side of the detector substrate. These dual-sided microstructured semiconductor neutron detectors (DS-MSNDs) have the ability to absorb and detect neutrons that stream through the front-side, effectively doubling the detection efficiency of a single-sided device. DS-MSND sensors are theoretically capable of achieving greater than 80% intrinsic thermal neutron detection efficiency for a 1-mm thick device. Prototype DS-MSNDs with diffused pvp-junction operated at 0-V applied bias have achieved 53.54±0.61%, exceeding that of the single-sided MSNDs and double-stacked MSNDs to represent a new record for detection efficiency for such solid-state devices. Advisors/Committee Members: Douglas S. McGregor.

Subjects/Keywords: Neutron; Radiation; Neutron detection; Radiation detection

…a neutron detection system. Pulses from events that rise above a lower-level discriminator… …radiation detectors due to the increased electric field strength. The (b) high… …wherein backfilled trenches improve neutron detection efficiency over thin-film-coated… …detection efficiency… …Fig. 3.2.4. Plotted are the simulated intrinsic thermal neutron detection efficiency for the…

14 more images…

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APA (6^th Edition):

Fronk, R. G. (2017). Dual-side etched microstructured semiconductor neutron detectors. (Doctoral Dissertation). Kansas State University. Retrieved from http://hdl.handle.net/2097/35426

Chicago Manual of Style (16^th Edition):

Fronk, Ryan G. “Dual-side etched microstructured semiconductor neutron detectors.” 2017. Doctoral Dissertation, Kansas State University. Accessed March 01, 2021. http://hdl.handle.net/2097/35426.

MLA Handbook (7^th Edition):

Fronk, Ryan G. “Dual-side etched microstructured semiconductor neutron detectors.” 2017. Web. 01 Mar 2021.

Vancouver:

Fronk RG. Dual-side etched microstructured semiconductor neutron detectors. [Internet] [Doctoral dissertation]. Kansas State University; 2017. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2097/35426.

Council of Science Editors:

Fronk RG. Dual-side etched microstructured semiconductor neutron detectors. [Doctoral Dissertation]. Kansas State University; 2017. Available from: http://hdl.handle.net/2097/35426

Colorado State University

17. Meengs, Matthew Richard. Detection of a weak radiological source in ambient background using spectral analysis.

Degree: MS(M.S.), Environmental and Radiological Health Sciences, 2018, Colorado State University

URL: http://hdl.handle.net/10217/191381

► The detection of radiation requires the use of statistical tools due to the probabilistic nature of the emission and interaction properties of radiation, an analysis… (more)

▼ The detection of radiation requires the use of statistical tools due to the probabilistic nature of the emission and interaction properties of radiation, an analysis that includes the testing of a hypothesis regarding the presence or absence of a source against background. Traditionally, a false positive rate of 5% is used to calculate a y*, the decision threshold, above which a source is determined to be present. However, in radiological conditions where a source is both improbable and weak, and where counting time is limited, detection of a source becomes increasingly challenging using this traditional method. The detection of clandestine fissile materials presents such a challenge, and with the increasing risk of nuclear proliferation, there exists a growing desire to research more optimal methods in detecting these sources, especially where a missed detection is of such high consequence. Previous research has shown that using a string of measurements, and calculating a detection limit based on a certain number of false positives within that string, consistently outperforms the traditional method of basing the detection limit on just one measurement. Such research to date has only been applied to counts of all energies (gross counts). The purpose of this research is to apply the success of this new detection algorithm to certain energies within the spectrum, and to discover whether further optimization is possible by this process. Optimization was evaluated using receiver operator characteristic (ROC) curves, where special emphasis was placed at the lower false positive values. Over the course of this research, two hypothesis were tested. The first hypothesis conjectures that it is indeed possible to further optimize source detection when using an energy bin other than gross counts. The second hypothesis postulates that if the first hypothesis is true, than there exists a mathematical criterion that predicts this behavior. Both hypothesis were verified to be correct. Advisors/Committee Members: Brandl, Alex (advisor), Johnson, Thomas (advisor), Kokoszka, Piotr (committee member).

Subjects/Keywords: detection of a weak source; new statistical algorithm for radiation detection; detection of a weak radiological source; spectral analysis; new methods of radiation detection

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Meengs, M. R. (2018). Detection of a weak radiological source in ambient background using spectral analysis. (Masters Thesis). Colorado State University. Retrieved from http://hdl.handle.net/10217/191381

Chicago Manual of Style (16^th Edition):

Meengs, Matthew Richard. “Detection of a weak radiological source in ambient background using spectral analysis.” 2018. Masters Thesis, Colorado State University. Accessed March 01, 2021. http://hdl.handle.net/10217/191381.

MLA Handbook (7^th Edition):

Meengs, Matthew Richard. “Detection of a weak radiological source in ambient background using spectral analysis.” 2018. Web. 01 Mar 2021.

Vancouver:

Meengs MR. Detection of a weak radiological source in ambient background using spectral analysis. [Internet] [Masters thesis]. Colorado State University; 2018. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/10217/191381.

Council of Science Editors:

Meengs MR. Detection of a weak radiological source in ambient background using spectral analysis. [Masters Thesis]. Colorado State University; 2018. Available from: http://hdl.handle.net/10217/191381

University of California – Berkeley

18. Yee, Ryan Matthew. Beta-delayed neutron spectroscopy using trapped radioactive ions.

Degree: Nuclear Engineering, 2013, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/5vk4z6bs

► A novel technique for beta-delayed neutron spectroscopy has been developed using trapped radioactive ions. The neutron energy spectrum was reconstructed by measuring the time of… (more)

Subjects/Keywords: Nuclear engineering; Nuclear physics; Decay spectroscopy; Ion trapping; Neutron detection; Radiation detection

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APA (6^th Edition):

Yee, R. M. (2013). Beta-delayed neutron spectroscopy using trapped radioactive ions. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/5vk4z6bs

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Yee, Ryan Matthew. “Beta-delayed neutron spectroscopy using trapped radioactive ions.” 2013. Thesis, University of California – Berkeley. Accessed March 01, 2021. http://www.escholarship.org/uc/item/5vk4z6bs.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Yee, Ryan Matthew. “Beta-delayed neutron spectroscopy using trapped radioactive ions.” 2013. Web. 01 Mar 2021.

Vancouver:

Yee RM. Beta-delayed neutron spectroscopy using trapped radioactive ions. [Internet] [Thesis]. University of California – Berkeley; 2013. [cited 2021 Mar 01]. Available from: http://www.escholarship.org/uc/item/5vk4z6bs.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Yee RM. Beta-delayed neutron spectroscopy using trapped radioactive ions. [Thesis]. University of California – Berkeley; 2013. Available from: http://www.escholarship.org/uc/item/5vk4z6bs

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Kansas State University

19. Edwards, Nathaniel Scott. ⁶Li-based suspended foil microstrip neutron detectors.

Degree: PhD, Department of Mechanical and Nuclear Engineering, 2018, Kansas State University

URL: http://hdl.handle.net/2097/39131

► The low natural abundance and supply shortage of ³He has resulted in an increase in the cost of ³He. The increase in cost of ³He… (more)

▼ The low natural abundance and supply shortage of ³He has resulted in an increase in the cost of ³He. The increase in cost of ³He proportional counters has motived the development of low cost, high efficiency, low gamma-ray sensitivity alternative technologies. A recently developed alternative technology is the ⁶Li-based suspended foil microstrip neutron detector (SFMND) that combines the neutron-conversion and gamma-ray discrimination capabilities of ⁶Li foils with the mechanical robustness and electrical capabilities of microstrip electrodes. SFMNDs differ from Li-foil multi-wire proportional counters because the anode wires are replaced by a single microstrip electrode that improves the mechanical robustness, reduces the microphonic sensitivity, and allows for more ⁶Li foils to be incorporated within a smaller form factor. The first-ever SFMNDs containing one and five 96%-enriched, 75-µm thick ⁶Li foils were fabricated using a silicon microstrip electrode. Neutron-sensitivity testing was performed yielding measured intrinsic thermal-neutron detection efficiencies, εth, of 4.02 ± 0.04% and 14.58 ± 0.11%, respectively. High electrode capacitance and gain instability were exhibited by the silicon microstrip electrode during neutron-sensitivity testing that led to the search for an electrically-stable microstrip-electrode substrate. Schott Borofloat® 33 glass was identified as an electrically-stable substrate and microstrip electrodes were fabricated and characterized. The Schott Borofloat® 33 microstrip electrodes were electrically-stable for a minimum duration of time of approximately 23 hours and had capacitances over an order of magnitude less than the identically sized silicon microstrip electrodes. One- and five-foil SFMNDs were fabricated with a Schott Borofloat® 33 microstrip electrode. Using 96%-enriched, 75-µm thick ⁶Li foils, the one- and five-foil devices had maximum measured εth of 12.58 ± 0.15% and 29.75 ± 0.26%, respectively, with measured gamma-ray rejection ratios of 6.46 x 10⁻⁵ ± 4.32 x 10⁻⁷ and 7.96 x 10-5 ± 4.65 x 10-7 for a ¹³⁷Cs exposure rate of 50 mR hr⁻¹. Devices containing one, five, ten, and twenty 96%-enriched, 75-µm thick ⁶Li foils were simulated using MCNP6 and are theoretically capable of having εth of 18.36%, 54.08%, 65.43%, and 68.36%, respectively. The deviation between measured and simulated εth is suspected to occur due to the electric field strength distribution, electron attachment, microstrip-electrode capacitance, or any combination thereof and solutions for each of these suspected concerns are described. Advisors/Committee Members: Douglas S. McGregor.

Subjects/Keywords: Neutron detection; Radiation detection; Microstrip electrodes; Lithium foil; Device characterization; Gas-filled neutron detector

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Edwards, N. S. (2018). ⁶Li-based suspended foil microstrip neutron detectors. (Doctoral Dissertation). Kansas State University. Retrieved from http://hdl.handle.net/2097/39131

Chicago Manual of Style (16^th Edition):

Edwards, Nathaniel Scott. “⁶Li-based suspended foil microstrip neutron detectors.” 2018. Doctoral Dissertation, Kansas State University. Accessed March 01, 2021. http://hdl.handle.net/2097/39131.

MLA Handbook (7^th Edition):

Edwards, Nathaniel Scott. “⁶Li-based suspended foil microstrip neutron detectors.” 2018. Web. 01 Mar 2021.

Vancouver:

Edwards NS. ⁶Li-based suspended foil microstrip neutron detectors. [Internet] [Doctoral dissertation]. Kansas State University; 2018. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2097/39131.

Council of Science Editors:

Edwards NS. ⁶Li-based suspended foil microstrip neutron detectors. [Doctoral Dissertation]. Kansas State University; 2018. Available from: http://hdl.handle.net/2097/39131

Kansas State University

20. Ochs, Taylor R. Advanced dual-sided microstructured semiconductor neutron detectors and instrumentation.

Degree: PhD, Department of Mechanical and Nuclear Engineering, 2020, Kansas State University

URL: http://hdl.handle.net/2097/40545

► Dual-Sided Microstructured Semiconductor Neutron Detectors (DS-MSNDs) have been developed as a viable alternative to expensive 3He for thermal-neutron detection. DS-MSNDs were designed as an advancement… (more)

▼ Dual-Sided Microstructured Semiconductor Neutron Detectors (DS-MSNDs) have been developed as a viable alternative to expensive 3He for thermal-neutron detection. DS-MSNDs were designed as an advancement on single-sided MSNDs which comprise high-aspect ratio trenches backfilled with 6LiF neutron conversion material etched deep into silicon pvn-junction diodes. Neutrons react in the conversion material, which produces energetic charged-particle reaction products that are measured in the adjacent silicon microfeatures. Single-sided MSNDs have been produced with an intrinsic thermal-neutron detection efficiency of 30-35% for normally incident neutrons, and the key limiting factor in detection efficiency is neutron free streaming paths through the neutron insensitive silicon fins. The DS-MSND incorporates a second set of 6LiF-backfilled trenches etched on the back-side of a thicker silicon diode that are offset from the front-side trenches to eliminate the neutron free streaming paths. Monte Carlo simulations show DS-MSNDs only 1.5-mm thick are theoretically capable of 80% intrinsic thermal-neutron detection efficiency, which could directly match commonly available 3He detectors. This work describes the design of DS-MSNDs including electric field modeling and microfeature geometry optimization with MCNP simulations, and fabrication process improvements implemented that elevate the state-of-the-art. The previous world record for intrinsic thermal-neutron detection efficiency for semiconductor neutron detectors was 53.5 ± 0.6%. Advancements in deep-trench etching and 6LiF backfilling methods presented herein have increased the current record intrinsic-thermal neutron detection efficiency to 69.3 ± 1.5%. Several prototype detector systems were fabricated implementing DS-MSND and MSND technology to aid in search and localization of special nuclear material. Drop-in replacements for small-diameter, high-pressure 3He detectors, and the DS-MSND-based HeRep Mk IV measured 80% to 115% of the count rate of a similarly sized 10-atm 3He detector based on the detector and source moderation configuration. Additionally, modular neutron detectors were developed for use in a high-sensitivity, low profile, wearable neutron detector for covert or overt source detection missions by warfighters, first responders, or law enforcement personnel. Additionally, MCNP simulations show the wearable detectors have potential to as operate as high-accuracy, real-time, neutron dose meters. The DS-MSND-based detector systems with on-board electronics offer a low-cost, low-power, compact, high sensitivity, alternative to 3He neutron detection. Advisors/Committee Members: Douglas S. McGregor.

Subjects/Keywords: Radiation detection; Helium-3 replacement; neutron detection; solid-state detector; Monte carlo modeling; Silicon processing

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APA (6^th Edition):

Ochs, T. R. (2020). Advanced dual-sided microstructured semiconductor neutron detectors and instrumentation. (Doctoral Dissertation). Kansas State University. Retrieved from http://hdl.handle.net/2097/40545

Chicago Manual of Style (16^th Edition):

Ochs, Taylor R. “Advanced dual-sided microstructured semiconductor neutron detectors and instrumentation.” 2020. Doctoral Dissertation, Kansas State University. Accessed March 01, 2021. http://hdl.handle.net/2097/40545.

MLA Handbook (7^th Edition):

Ochs, Taylor R. “Advanced dual-sided microstructured semiconductor neutron detectors and instrumentation.” 2020. Web. 01 Mar 2021.

Vancouver:

Ochs TR. Advanced dual-sided microstructured semiconductor neutron detectors and instrumentation. [Internet] [Doctoral dissertation]. Kansas State University; 2020. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2097/40545.

Council of Science Editors:

Ochs TR. Advanced dual-sided microstructured semiconductor neutron detectors and instrumentation. [Doctoral Dissertation]. Kansas State University; 2020. Available from: http://hdl.handle.net/2097/40545

University of Illinois – Urbana-Champaign

21. Zircher, Christian Donald. Radiation network within a virtual environment.

Degree: MS, Nuclear, Plasma, Radiolgc Engr, 2017, University of Illinois – Urbana-Champaign

URL: http://hdl.handle.net/2142/97462

► Radiation sensor networks play a key role in the detection, localization, and ultimately prevention of nuclear threats. These sensor networks create large amounts of data… (more)

▼ Radiation sensor networks play a key role in the detection, localization, and ultimately prevention of nuclear threats. These sensor networks create large amounts of data that must be processed. Currently, there are studies focusing on how to collect, analyze, and visualize these large amounts of data. The goal of the Radiation Sensor Network within a Virtual Environment is to visualize the data collected from a radiation sensor network in real-time and in such a way that experts as well as non-experts can fully utilize the information. This thesis begins by presenting existing data presentation methods before proposing its own solution. Next the radiation sensor network used for this project is described along with the storage system for the network's data. We then discuss the game engine, Unity, used to host the virtual environment along with its purposes and abilities, which includes scripting, additional modeling, and detailing. An alternative game engine, Amazon Lumberyard, is discussed as well as a possible replacement for Unity due to its native integration to the cloud computing services used for the network's data storage. Next, the area needed to be modeled is presented along with the methods used for the 3D modeling. The computer software, SketchUp, is used for the majority of the modeling, such as the buildings and terrain. Alternative methods utilizing photogrammetry and or inferred scanning used for objects of complex geometries are also presented. The data acquisition process is then presented, which includes multiple scripts used to pull data from cloud storage and transform it into a format readable to the game engine. The next section discusses the techniques used to visualize the geospatial data within the virtual environment. This is done by converting the latitude longitude coordinates collected from each sensor node into the Cartesian format used by the game engine. Movement of the detectors is visualized using a method called "Waypoint Based Movement" which effectively interpolates the geospatial data points. We then focus on the multiple visualization techniques developed to display the data collected from a radiation sensor network in real-time. The methods include both 2D and 3D visualizations which utilize either or both heat maps and height maps as well as an alarm system. This thesis concludes with proposals for future work on other visualization techniques as well as decreasing the time between data collection and data visualization. Advisors/Committee Members: Sullivan, Clair J (advisor), Uddin, Rizwan (committee member).

Subjects/Keywords: Radiation sensor network; Mobile sensor network; Radiation detection; 3D radiation visualization; Live-time radiation monitoring; Live data visualization; Unity 3D; SketchUp; Radiation map

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APA (6^th Edition):

Zircher, C. D. (2017). Radiation network within a virtual environment. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/97462

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Zircher, Christian Donald. “Radiation network within a virtual environment.” 2017. Thesis, University of Illinois – Urbana-Champaign. Accessed March 01, 2021. http://hdl.handle.net/2142/97462.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Zircher, Christian Donald. “Radiation network within a virtual environment.” 2017. Web. 01 Mar 2021.

Vancouver:

Zircher CD. Radiation network within a virtual environment. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2017. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2142/97462.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Zircher CD. Radiation network within a virtual environment. [Thesis]. University of Illinois – Urbana-Champaign; 2017. Available from: http://hdl.handle.net/2142/97462

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

University of California – Berkeley

22. Galloway, Michelle. Characterization and Applications of a CdZnTe-Based Multimode Imager.

Degree: Nuclear Engineering, 2014, University of California – Berkeley

URL: http://www.escholarship.org/uc/item/92s4p2z6

► Detection of electromagnetic radiation in the form of gamma rays provides a means to discover the presence of nuclear sources and the occurrence of highly-energetic… (more)

▼ Detection of electromagnetic radiation in the form of gamma rays provides a means to discover the presence of nuclear sources and the occurrence of highly-energetic events that occur in our terrestrial and astrophysical environment. The highly penetrative nature ofgamma rays allows for probing into objects and regions that are obscured at other wavelengths. The detection and imaging of gamma rays relies upon an understanding of the ways in which these high-energy photons interact with matter.The applications of gamma-ray detection and imaging are numerous. Astrophysical observation of gamma rays expands our understanding of the Universe in which we live. Terrestrial detection and imaging of gamma rays enable environmental monitoring of radioactivity. This allows for identification and localization of nuclear materials to prevent illicit trafficking and to ultimately protect against harmful acts. Additionally, terrestrial-based detection is essential, for example, in monitoring the widespread contamination within the Fukushima prefecture in Japan as a result of a nuclear power plant accident.This dissertation focusses on the development and characterization of a gamma-ray detection and imaging instrument and explores its capabilities for the aforementioned applications. The High Efficiency Multimode Imager, HEMI, is a prototype instrument that is based on Cadmium Zinc Telluride (CdZnTe) semiconductor detectors. The detectors are arranged in a two-planar configuration to allow for both Compton and coded-aperture imaging. The front plane consists of active detectors in a random mask pattern to serve simultaneously as a coded mask and a Compton scatter plane, thus providing high detection efficiency. The use of multimode imaging extends the energy range to allow for localization of sources with gamma-ray emissions from tens of keV to a few MeV. HEMI was initially developed as a prototype instrument to demonstrate its capabilities for nuclear threat detection, spectroscopy, and imaging. The 96-detector instrument was developed and fully characterized within the laboratory environment, yielding a system energy resolution of 2.4% FWHM at 662 keV, an angular resolution of 9.5 deg. FWHM at 662 keV in Compton mode, and a 10.6 deg. angular resolution in coded aperture mode. After event cuts, the effective area for Compton imaging of the 662 keV photopeak is 0.1 cm ²2. Imaging of point sources in both Compton and coded aperture modes have been demonstrated. The minimum detectable activity of a ¹³⁷Cs at a 20 m distance with 20 seconds of observation time is estimated to be 0.2 mCi in spectral mode and 20 mCi in Compton imaging mode.These performance parameters fulfilled the requirements of the nuclear security program.Following the Fukushima Dai-ichi Nuclear Power Plant accident of March, 2011, efficient methods to assess levels of radioactive contamination over large areas are needed to aid in clean-up efforts. Although a field study was not initially intended for the HEMI prototype, its…

Subjects/Keywords: Nuclear engineering; CdZnTe; Detection; Gamma-ray; HEMI; imager; Radiation

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APA (6^th Edition):

Galloway, M. (2014). Characterization and Applications of a CdZnTe-Based Multimode Imager. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/92s4p2z6

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Galloway, Michelle. “Characterization and Applications of a CdZnTe-Based Multimode Imager.” 2014. Thesis, University of California – Berkeley. Accessed March 01, 2021. http://www.escholarship.org/uc/item/92s4p2z6.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Galloway, Michelle. “Characterization and Applications of a CdZnTe-Based Multimode Imager.” 2014. Web. 01 Mar 2021.

Vancouver:

Galloway M. Characterization and Applications of a CdZnTe-Based Multimode Imager. [Internet] [Thesis]. University of California – Berkeley; 2014. [cited 2021 Mar 01]. Available from: http://www.escholarship.org/uc/item/92s4p2z6.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Galloway M. Characterization and Applications of a CdZnTe-Based Multimode Imager. [Thesis]. University of California – Berkeley; 2014. Available from: http://www.escholarship.org/uc/item/92s4p2z6

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

UCLA

23. Chen, Qi. Polymer Composites for Radiation Scintillation.

Degree: Materials Science and Engineering, 2012, UCLA

URL: http://www.escholarship.org/uc/item/5jd591ct

► The dissertation is focused on composite scintillating materials for gamma-ray and fast neutron spectroscopy. The inorganic-organic composite scintillators have been successfully fabricated and investigated. By… (more)

Subjects/Keywords: Materials Science; conjugated polymers; gamma; nanocrystals; neutron; radiation detection; scintillator

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APA (6^th Edition):

Chen, Q. (2012). Polymer Composites for Radiation Scintillation. (Thesis). UCLA. Retrieved from http://www.escholarship.org/uc/item/5jd591ct

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Chen, Qi. “Polymer Composites for Radiation Scintillation.” 2012. Thesis, UCLA. Accessed March 01, 2021. http://www.escholarship.org/uc/item/5jd591ct.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Chen, Qi. “Polymer Composites for Radiation Scintillation.” 2012. Web. 01 Mar 2021.

Vancouver:

Chen Q. Polymer Composites for Radiation Scintillation. [Internet] [Thesis]. UCLA; 2012. [cited 2021 Mar 01]. Available from: http://www.escholarship.org/uc/item/5jd591ct.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Chen Q. Polymer Composites for Radiation Scintillation. [Thesis]. UCLA; 2012. Available from: http://www.escholarship.org/uc/item/5jd591ct

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Rochester Institute of Technology

24. Laffey, Luke John. An Analysis of the Scintillation Properties of Several Materials for Radiation Detection.

Degree: MS, School of Chemistry and Materials Science (COS), 2020, Rochester Institute of Technology

URL: https://scholarworks.rit.edu/theses/10482

► The accurate detection and identification of ionizing radiation and radioisotopes is of significant interest to governments, industry and the scientific community, particularly for use… (more)

Subjects/Keywords: Inorganic; Plastic; Pulse shape discrimination; Radiation detection; Scintillator

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APA (6^th Edition):

Laffey, L. J. (2020). An Analysis of the Scintillation Properties of Several Materials for Radiation Detection. (Masters Thesis). Rochester Institute of Technology. Retrieved from https://scholarworks.rit.edu/theses/10482

Chicago Manual of Style (16^th Edition):

Laffey, Luke John. “An Analysis of the Scintillation Properties of Several Materials for Radiation Detection.” 2020. Masters Thesis, Rochester Institute of Technology. Accessed March 01, 2021. https://scholarworks.rit.edu/theses/10482.

MLA Handbook (7^th Edition):

Laffey, Luke John. “An Analysis of the Scintillation Properties of Several Materials for Radiation Detection.” 2020. Web. 01 Mar 2021.

Vancouver:

Laffey LJ. An Analysis of the Scintillation Properties of Several Materials for Radiation Detection. [Internet] [Masters thesis]. Rochester Institute of Technology; 2020. [cited 2021 Mar 01]. Available from: https://scholarworks.rit.edu/theses/10482.

Council of Science Editors:

Laffey LJ. An Analysis of the Scintillation Properties of Several Materials for Radiation Detection. [Masters Thesis]. Rochester Institute of Technology; 2020. Available from: https://scholarworks.rit.edu/theses/10482

University of Michigan

25. Marcath, Matthew. Measured and Simulated Prompt Fission Neutron and Photon Correlations.

Degree: PhD, Nuclear Engineering & Radiological Sciences, 2018, University of Michigan

URL: http://hdl.handle.net/2027.42/147560

► An accurate understanding of fission is critical to characterization of special nuclear material (SNM) for nonproliferation and safeguards applications. Noninvasive and nondestructive techniques rely primarily… (more)

▼ An accurate understanding of fission is critical to characterization of special nuclear material (SNM) for nonproliferation and safeguards applications. Noninvasive and nondestructive techniques rely primarily on highly penetrating and relatively abundant fission emissions. Spontaneously and under particle interrogation, SNM emits neutrons and photons from fission, which are characteristic of the fissioning isotopes. Characteristic neutrons and photons are emitted from nuclear fission when a deformed, neutron-rich nucleus divides into two fragments that then de-excite. During de-excitation, neutrons are emitted first, followed by photons; this process gives rise to correlations. New, event-by-event, physics-based models, CGMF (Los Alamos National Laboratory) and FREYA (Lawrence Livermore National Laboratory), predict correlations in prompt fission emissions. Current safeguards and nonproliferation systems do not utilize angular or multiplicity correlations. Little data exist to validate these models; correlated quantities have been measured only for 252Cf(sf). My work provides measured correlation data to validate models useful for future system design. Previous correlation measurements have been limited by the acquisition challenges of a many-detector array and therefore have used simple detector systems. Additionally, few detection methods exist that are simultaneously efficient to neutrons and photons. In this work, I show a many-detector array of pulse-shape-discrimination-capable organic scintillators, sensitive to both fast neutrons and photons, to measure correlations in neutron energy, photon energy, multiplicity, and emission angle. This work is achieved through MCNPX-PoliMi simulations and through use of time-synchronized, high-throughput, multiple-digitizer acquisition systems. I performed experiments sensitive to correlations with a large array of organic scintillators. I performed measurements of 252Cf(sf) at both the University of Michigan and the Los Alamos National Laboratory; and of 240Pu(sf) at the Joint Research Centre in Ispra, Italy, and at the Los Alamos National Laboratory. I measured the 240Pu(sf) neutron-neutron angular distribution and found it to be less anisotropic than the 252Cf(sf) neutrons. 240Pu(sf) and 252Cf(sf) neutron-neutron angular distribution simulation results indicate that fission models capture the general trend of neutron anisotropy. 240Pu(sf) and 252Cf(sf) experimental multiplicity results suggest weak neutron-photon competition during fragment de-excitation. The measured correlations were compared with MCNPX-PoliMi simulations using the built-in model and two new event-by-event fission models, CGMF and FREYA, which predict correlations in prompt emissions from fission. Simulation results from CGMF and FREYA predict a stronger negative correlation than the experiment result. Advisors/Committee Members: Pozzi, Sara A (committee member), Lorenzon, Wolfgang B (committee member), Haight, Robert C (committee member), Larsen, Edward W (committee member).

Subjects/Keywords: nuclear engineering; fission; radiation detection; Nuclear Engineering and Radiological Sciences; Engineering

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Marcath, M. (2018). Measured and Simulated Prompt Fission Neutron and Photon Correlations. (Doctoral Dissertation). University of Michigan. Retrieved from http://hdl.handle.net/2027.42/147560

Chicago Manual of Style (16^th Edition):

Marcath, Matthew. “Measured and Simulated Prompt Fission Neutron and Photon Correlations.” 2018. Doctoral Dissertation, University of Michigan. Accessed March 01, 2021. http://hdl.handle.net/2027.42/147560.

MLA Handbook (7^th Edition):

Marcath, Matthew. “Measured and Simulated Prompt Fission Neutron and Photon Correlations.” 2018. Web. 01 Mar 2021.

Vancouver:

Marcath M. Measured and Simulated Prompt Fission Neutron and Photon Correlations. [Internet] [Doctoral dissertation]. University of Michigan; 2018. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2027.42/147560.

Council of Science Editors:

Marcath M. Measured and Simulated Prompt Fission Neutron and Photon Correlations. [Doctoral Dissertation]. University of Michigan; 2018. Available from: http://hdl.handle.net/2027.42/147560

Texas A&M University

26. Emery, Grant. Remotely Accessible Radiation Detection Laboratory for Distance Education.

Degree: MS, Nuclear Engineering, 2018, Texas A&M University

URL: http://hdl.handle.net/1969.1/173551

► An essential part of any student’s curriculum in nuclear engineering is performing radiation detection experiments to gain a better understanding of the physical processes that… (more)

Subjects/Keywords: Nuclear Engineering; Radiation Detection; Distance Education; Remote Control

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APA (6^th Edition):

Emery, G. (2018). Remotely Accessible Radiation Detection Laboratory for Distance Education. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173551

Chicago Manual of Style (16^th Edition):

Emery, Grant. “Remotely Accessible Radiation Detection Laboratory for Distance Education.” 2018. Masters Thesis, Texas A&M University. Accessed March 01, 2021. http://hdl.handle.net/1969.1/173551.

MLA Handbook (7^th Edition):

Emery, Grant. “Remotely Accessible Radiation Detection Laboratory for Distance Education.” 2018. Web. 01 Mar 2021.

Vancouver:

Emery G. Remotely Accessible Radiation Detection Laboratory for Distance Education. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/1969.1/173551.

Council of Science Editors:

Emery G. Remotely Accessible Radiation Detection Laboratory for Distance Education. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173551

Texas A&M University

27. Erchinger, Jennifer. Investigating the Operational Capabilities of Custom and Pedestrian Portal Monitoring Systems for Screening Livestock for Radioactive Contamination.

Degree: MS, Health Physics, 2013, Texas A&M University

URL: http://hdl.handle.net/1969.1/149544

► Livestock and companion animals are valuable economically and emotionally in the economy of many states and to their citizens. In a radiological emergency situation, the… (more)

▼ Livestock and companion animals are valuable economically and emotionally in the economy of many states and to their citizens. In a radiological emergency situation, the loss of a large amount of livestock could be devastating to a state or national economy. If such an event occurred, there are currently no screening and decontamination protocols for the handling of livestock. This research investigated current policies and procedures for monitoring and decontamination of livestock and companion animals, as well as testing pedestrian portal monitors and a newly designed livestock portal capable of radionuclide identification. It was discovered that only ten states addressed companion animals or livestock anywhere in their emergency planning. Of the ten, only North Carolina, Washington, and a Massachusetts K9 unit had detailed decontamination procedures to report for companion animals. None of the states included detailed procedures for livestock. To address livestock screening, three pedestrian portal monitoring systems were tested in the field and lab trials – the Johnson AM801, TSA TPM903A, and Ludlum 52-1-1. The systems were tested for position and count rate sensitivity with 1 and 5 µCi 137Cs sources placed on four locations on a steer. Factors such as operability and ease of use were also considered. All three systems would alarm when a 5 µCi 137Cs source was used and the occupancy sensor was triggered. The Johnson AM801 system was determined to be the most appropriate for use in livestock screening due to sensitive alarm algorithms, greater position discrimination with four detectors, and ease of adjustment for agricultural purposes. The last phase of this project included designing and constructing a portal system that included radionuclide identification capabilities. An array of six sodium iodide detectors was mounted on a panel and field-tested beside a cattle chute and in a walkway. The custom portal, the Bovine Screening Portal (BSP), observed increased count rates (>10σ) from a 5 µCi 137Cs source in live time. The BSP demonstrated better detection and localization of the source and spectral identification capabilities compared to the commercially available pedestrian systems. Advisors/Committee Members: Marianno, Craig (advisor), Poston, John (committee member), Herring, Andy (committee member).

Subjects/Keywords: livestock; radiation detection; livestock portal monitor; pedestrian portal monitor

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APA (6^th Edition):

Erchinger, J. (2013). Investigating the Operational Capabilities of Custom and Pedestrian Portal Monitoring Systems for Screening Livestock for Radioactive Contamination. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/149544

Chicago Manual of Style (16^th Edition):

Erchinger, Jennifer. “Investigating the Operational Capabilities of Custom and Pedestrian Portal Monitoring Systems for Screening Livestock for Radioactive Contamination.” 2013. Masters Thesis, Texas A&M University. Accessed March 01, 2021. http://hdl.handle.net/1969.1/149544.

MLA Handbook (7^th Edition):

Erchinger, Jennifer. “Investigating the Operational Capabilities of Custom and Pedestrian Portal Monitoring Systems for Screening Livestock for Radioactive Contamination.” 2013. Web. 01 Mar 2021.

Vancouver:

Erchinger J. Investigating the Operational Capabilities of Custom and Pedestrian Portal Monitoring Systems for Screening Livestock for Radioactive Contamination. [Internet] [Masters thesis]. Texas A&M University; 2013. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/1969.1/149544.

Council of Science Editors:

Erchinger J. Investigating the Operational Capabilities of Custom and Pedestrian Portal Monitoring Systems for Screening Livestock for Radioactive Contamination. [Masters Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/149544

Penn State University

28. Cazalas, Edward Jay. Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures.

Degree: 2015, Penn State University

URL: https://submit-etda.libraries.psu.edu/catalog/24270

► An important contemporary motivation for advancing radiation detection science and technology is the need for interdiction of nuclear and radiological materials, which may be used… (more)

▼ An important contemporary motivation for advancing radiation detection science and technology is the need for interdiction of nuclear and radiological materials, which may be used to fabricate weapons of mass destruction. The detection of such materials by nuclear techniques relies on achieving high sensitivity and selectivity to X-rays, gamma-rays, and neutrons. To be attractive in field deployable instruments, it is desirable for detectors to be lightweight, inexpensive, operate at low voltage, and consume low power. To address the relatively low particle flux in most passive measurements for nuclear security applications, detectors scalable to large areas that can meet the high absolute detection efficiency requirements are needed. Graphene-based and thin-film-based radiation detectors represent attractive technologies that could meet the need for inexpensive, low-power, size-scalable detection architectures, which are sensitive to X-rays, �gamma-rays, and neutrons. The utilization of graphene to detect ionizing radiation relies on the modulation of graphene charge carrier density by changes in local electric field, i.e. the field effect in graphene. Built on the principle of a conventional field effect transistor, the graphene-based field effect transistor (GFET) utilizes graphene as a channel and a semiconducting substrate as an absorber medium with which the ionizing radiation interacts. A radiation interaction event that deposits energy within the substrate creates electron-hole pairs, which modify the electric field and modulate graphene charge carrier density. A detection event in a GFET is therefore measured as a change in graphene resistance or current. Thin (micron-scale) films can also be utilized for radiation detection of thermal neutrons provided nuclides with high neutron absorption cross section are present with appreciable density. Detection in thin-film detectors could be realized through the collection of charge carriers generated within the film by slowing-down of neutron capture reaction products. The objective of this dissertation is to develop, characterize, and optimize novel graphene-based and thin-film radiation detectors. The dissertation includes a review of relevant physics, comprehensive descriptions and discussions of the experimental campaigns that were conducted, computational simulations, and detailed analysis of certain processes occurring in graphene-based and thin-film radiation detectors that significantly affect their response characteristics. Experiments have been conducted to characterize the electrical properties of GFETs and their responsivity to radiation of different types, such as visible, ultraviolet, X-ray, and gamma�-ray photons, and alpha particles. The nature of graphene hysteretic effects under operational conditions has been studied. Spatially dependent sensitivity of GFETs to irradiation has been experimentally investigated using both a focused laser beam and focused X-ray microbeam. A model has been developed that deterministically simulates the mechanisms of… Advisors/Committee Members: Igor Jovanovic, Dissertation Advisor/Co-Advisor, Igor Jovanovic, Committee Chair/Co-Chair, Joshua Alexander Robinson, Committee Member, Yong Chen, Special Member, Arthur Thompson Motta, Committee Member, Kenan Unlu, Committee Member.

Subjects/Keywords: graphene; field effect transistor; neutron; detection; radiation; thin film; hysteresis

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APA (6^th Edition):

Cazalas, E. J. (2015). Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/24270

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Cazalas, Edward Jay. “Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures.” 2015. Thesis, Penn State University. Accessed March 01, 2021. https://submit-etda.libraries.psu.edu/catalog/24270.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Cazalas, Edward Jay. “Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures.” 2015. Web. 01 Mar 2021.

Vancouver:

Cazalas EJ. Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures. [Internet] [Thesis]. Penn State University; 2015. [cited 2021 Mar 01]. Available from: https://submit-etda.libraries.psu.edu/catalog/24270.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Cazalas EJ. Radiation Sensitivity of Graphene Field Effect Transistors and Other Thin Film Architectures. [Thesis]. Penn State University; 2015. Available from: https://submit-etda.libraries.psu.edu/catalog/24270

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Penn State University

29. Vresko, Brian Andrew. Supporting Analysis for the Development of a Reconfigurable Dipole Chaff Element for the Remote Passive Detection of Neutrons.

Degree: 2012, Penn State University

URL: https://submit-etda.libraries.psu.edu/catalog/15524

► The objective of thesis research was to evaluate potential candidate materials that were under consideration in the development of a new neutron detecting device. This… (more)

▼ The objective of thesis research was to evaluate potential candidate materials that were under consideration in the development of a new neutron detecting device. This project was inspired by a detector that consisted of reconfigurable dipole chaff elements for the remote passive detection of chemical agents. It was proposed that a similar detector could be developed to detect neutrons instead of chemicals, by modifying radiosensitive material and adding a neutron converter. The radiosensitive material that was being considered for the neutron detector design was the diacetylene, PCDA. The three different converter materials that were considered for the detector design were gadolinium metal, boron nitride, and lithium silicate. A number of important observations were made from the experiments performed in this study. The results obtained from the gamma irradiation experiments indicated that the incorporation of gadolinium in the PCDA samples increased the materials’ gamma-ray sensitivity. This increased sensitivity was not desirable, since a goal for the detector design was for it to be insensitive to background radiation. The neutron irradiation experiments showed that the radiosensitive material should not be thicker than the range of the ions or charged particles, generated by a neutron-converter interaction. Additionally, there should be a distinct layer of converter material in the detector design, instead of a distribution of converter nanoparticles in the radiosensitive material. Because the amount of neutron converter that can be incorporated in the PCDA is limited, utilizing a discrete layer of converter increases the number of converter atoms. For a given flux, this yields an increased number of neutron absorptions, and therefore increases the energy that can be emitted from the converter into the PCDA. Models of the converter and the radiosensitive material were utilized to determine the neutron interaction distributions in the converter and the reaction product interaction in the radiosensitive material. The Monte Carlo methods based computer programs CASINO and SRIM were used to model the produced electrons and heavy charged particles, respectively. Because the converters were thin, neutron interactions within the converters were modeled assuming simple exponential attenuation. The modeling indicated that different converter materials should be incorporated into the detector design depending on the design limitations and how the device is to be deployed. If boron nitride is used as the converter material in the detector design, the PCDA radiosensitive material thickness should be set to 5 microns and the boron nitride thickness should be equal to or greater than 10 microns. When gadolinium metal foil is used as the converter, the PCDA radiosensitive material should be set to 50 microns and the gadolinium thickness should be equal to or greater than 10 microns. In the case where lithium silicate is used as the converter material, the radiosensitive material thickness should be set to 50… Advisors/Committee Members: Jack Brenizer Jr., Thesis Advisor/Co-Advisor.

Subjects/Keywords: neutron; detection; detector; antenna; PCDA; converter; gadolinium; boron; lithium; radiosensitive; radiation

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

Vresko, B. A. (2012). Supporting Analysis for the Development of a Reconfigurable Dipole Chaff Element for the Remote Passive Detection of Neutrons. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/15524

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Chicago Manual of Style (16^th Edition):

Vresko, Brian Andrew. “Supporting Analysis for the Development of a Reconfigurable Dipole Chaff Element for the Remote Passive Detection of Neutrons.” 2012. Thesis, Penn State University. Accessed March 01, 2021. https://submit-etda.libraries.psu.edu/catalog/15524.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

MLA Handbook (7^th Edition):

Vresko, Brian Andrew. “Supporting Analysis for the Development of a Reconfigurable Dipole Chaff Element for the Remote Passive Detection of Neutrons.” 2012. Web. 01 Mar 2021.

Vancouver:

Vresko BA. Supporting Analysis for the Development of a Reconfigurable Dipole Chaff Element for the Remote Passive Detection of Neutrons. [Internet] [Thesis]. Penn State University; 2012. [cited 2021 Mar 01]. Available from: https://submit-etda.libraries.psu.edu/catalog/15524.

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

Council of Science Editors:

Vresko BA. Supporting Analysis for the Development of a Reconfigurable Dipole Chaff Element for the Remote Passive Detection of Neutrons. [Thesis]. Penn State University; 2012. Available from: https://submit-etda.libraries.psu.edu/catalog/15524

Note: this citation may be lacking information needed for this citation format:
Not specified: Masters Thesis or Doctoral Dissertation

30. -8078-0075. Portable amplifier for semiconductor-based radiation detectors.

Degree: MSin Electrical Engineering, Engineering, 2016, Texas Tech University

URL: http://hdl.handle.net/2346/72359

► Research was conducted to build a portable radiation detector on printed circuit board (PCB) level. The history of detecting gamma radiation and neutrons is briefly… (more)

Subjects/Keywords: Radiation Detector; Neutron Detection

…Neutron and Gamma Detection Background Radiation detection is used in several different fields… …such as astronomy, medical, defense and others. One major use for radiation detection is to… …concerning parameters of semiconductor devices used for radiation detection. The junction… …gamma radiation. It was thought that if the portable device would work well with detecting… …gamma radiation, the portable device could eventually be implemented with the neutron detector…

11 more images…

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APA · Chicago · MLA · Vancouver · CSE | Export to Zotero / EndNote / Reference Manager

APA (6^th Edition):

-8078-0075. (2016). Portable amplifier for semiconductor-based radiation detectors. (Masters Thesis). Texas Tech University. Retrieved from http://hdl.handle.net/2346/72359

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Chicago Manual of Style (16^th Edition):

-8078-0075. “Portable amplifier for semiconductor-based radiation detectors.” 2016. Masters Thesis, Texas Tech University. Accessed March 01, 2021. http://hdl.handle.net/2346/72359.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

MLA Handbook (7^th Edition):

-8078-0075. “Portable amplifier for semiconductor-based radiation detectors.” 2016. Web. 01 Mar 2021.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Vancouver:

-8078-0075. Portable amplifier for semiconductor-based radiation detectors. [Internet] [Masters thesis]. Texas Tech University; 2016. [cited 2021 Mar 01]. Available from: http://hdl.handle.net/2346/72359.

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

Council of Science Editors:

-8078-0075. Portable amplifier for semiconductor-based radiation detectors. [Masters Thesis]. Texas Tech University; 2016. Available from: http://hdl.handle.net/2346/72359

Note: this citation may be lacking information needed for this citation format:
Author name may be incomplete

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Open Access Theses and Dissertations