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You searched for subject:(neutron flux). Showing records 1 – 30 of 49 total matches.

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University of Texas – Austin

1. -4066-2303. Development of an in-core neutron monitoring system and characterization of the University of Texas at Austin TRIGA reactor steady-state neutron flux variations for use with Neutron Activation Analysis.

Degree: Mechanical Engineering, 2018, University of Texas – Austin

 The pneumatic NAA facility within The University of Texas at Austin is widely used for the measurement of trace elemental concentrations. It has been shown… (more)

Subjects/Keywords: Neutron flux monitoring; Neutron Activation Analysis; Neutron flux variance

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APA (6th Edition):

-4066-2303. (2018). Development of an in-core neutron monitoring system and characterization of the University of Texas at Austin TRIGA reactor steady-state neutron flux variations for use with Neutron Activation Analysis. (Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/69096

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

Chicago Manual of Style (16th Edition):

-4066-2303. “Development of an in-core neutron monitoring system and characterization of the University of Texas at Austin TRIGA reactor steady-state neutron flux variations for use with Neutron Activation Analysis.” 2018. Thesis, University of Texas – Austin. Accessed June 17, 2019. http://hdl.handle.net/2152/69096.

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

MLA Handbook (7th Edition):

-4066-2303. “Development of an in-core neutron monitoring system and characterization of the University of Texas at Austin TRIGA reactor steady-state neutron flux variations for use with Neutron Activation Analysis.” 2018. Web. 17 Jun 2019.

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

Vancouver:

-4066-2303. Development of an in-core neutron monitoring system and characterization of the University of Texas at Austin TRIGA reactor steady-state neutron flux variations for use with Neutron Activation Analysis. [Internet] [Thesis]. University of Texas – Austin; 2018. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/2152/69096.

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

Council of Science Editors:

-4066-2303. Development of an in-core neutron monitoring system and characterization of the University of Texas at Austin TRIGA reactor steady-state neutron flux variations for use with Neutron Activation Analysis. [Thesis]. University of Texas – Austin; 2018. Available from: http://hdl.handle.net/2152/69096

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


Clemson University

2. Willey, Adam Hunter. Thermal Neutron Characterization and Dose Modeling of a Plutonium-239/Beryllium Alpha-Neutron Source.

Degree: MS, Environmental Engineering and Earth Sciences, 2018, Clemson University

 Determination of neutron dose can be challenging and requires knowledge of neutron energy and neutron flux. A plutonium-239/beryllium (239PuBe) alpha-neutron source was used to irradiate… (more)

Subjects/Keywords: Activation; Alpha Neutron Source; Neutron Dose; Neutron Flux; Thermal Neutron

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APA (6th Edition):

Willey, A. H. (2018). Thermal Neutron Characterization and Dose Modeling of a Plutonium-239/Beryllium Alpha-Neutron Source. (Masters Thesis). Clemson University. Retrieved from https://tigerprints.clemson.edu/all_theses/3023

Chicago Manual of Style (16th Edition):

Willey, Adam Hunter. “Thermal Neutron Characterization and Dose Modeling of a Plutonium-239/Beryllium Alpha-Neutron Source.” 2018. Masters Thesis, Clemson University. Accessed June 17, 2019. https://tigerprints.clemson.edu/all_theses/3023.

MLA Handbook (7th Edition):

Willey, Adam Hunter. “Thermal Neutron Characterization and Dose Modeling of a Plutonium-239/Beryllium Alpha-Neutron Source.” 2018. Web. 17 Jun 2019.

Vancouver:

Willey AH. Thermal Neutron Characterization and Dose Modeling of a Plutonium-239/Beryllium Alpha-Neutron Source. [Internet] [Masters thesis]. Clemson University; 2018. [cited 2019 Jun 17]. Available from: https://tigerprints.clemson.edu/all_theses/3023.

Council of Science Editors:

Willey AH. Thermal Neutron Characterization and Dose Modeling of a Plutonium-239/Beryllium Alpha-Neutron Source. [Masters Thesis]. Clemson University; 2018. Available from: https://tigerprints.clemson.edu/all_theses/3023


Texas A&M University

3. Johnson, Matthew Paul. Application of Next-Generation Sensor Systems in HTRs.

Degree: 2013, Texas A&M University

 Accurate knowledge of the neutron flux distribution in a nuclear reactor has many tangible benefits. Perhaps the most important are the contributions to reactor safety.… (more)

Subjects/Keywords: HTR; sensors; neutron flux reconstruction

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APA (6th Edition):

Johnson, M. P. (2013). Application of Next-Generation Sensor Systems in HTRs. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/149621

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

Chicago Manual of Style (16th Edition):

Johnson, Matthew Paul. “Application of Next-Generation Sensor Systems in HTRs.” 2013. Thesis, Texas A&M University. Accessed June 17, 2019. http://hdl.handle.net/1969.1/149621.

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

MLA Handbook (7th Edition):

Johnson, Matthew Paul. “Application of Next-Generation Sensor Systems in HTRs.” 2013. Web. 17 Jun 2019.

Vancouver:

Johnson MP. Application of Next-Generation Sensor Systems in HTRs. [Internet] [Thesis]. Texas A&M University; 2013. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/1969.1/149621.

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

Council of Science Editors:

Johnson MP. Application of Next-Generation Sensor Systems in HTRs. [Thesis]. Texas A&M University; 2013. Available from: http://hdl.handle.net/1969.1/149621

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


Oregon State University

4. Robinson, Cheryl A. Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels.

Degree: MS, Nuclear Engineering, 1981, Oregon State University

 Through a joint effort by the Swiss Federal Institute for Reactor Research and Oregon State University, the fuels modeling code SPECKLE is being developed to… (more)

Subjects/Keywords: Neutron flux

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APA (6th Edition):

Robinson, C. A. (1981). Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/42178

Chicago Manual of Style (16th Edition):

Robinson, Cheryl A. “Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels.” 1981. Masters Thesis, Oregon State University. Accessed June 17, 2019. http://hdl.handle.net/1957/42178.

MLA Handbook (7th Edition):

Robinson, Cheryl A. “Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels.” 1981. Web. 17 Jun 2019.

Vancouver:

Robinson CA. Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels. [Internet] [Masters thesis]. Oregon State University; 1981. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/1957/42178.

Council of Science Editors:

Robinson CA. Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels. [Masters Thesis]. Oregon State University; 1981. Available from: http://hdl.handle.net/1957/42178


University of Arizona

5. Boettinger, William Leo, 1939-. Neutron flux in the vicinity of a reactor control rod .

Degree: 1963, University of Arizona

Subjects/Keywords: Neutron flux.

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APA (6th Edition):

Boettinger, William Leo, 1. (1963). Neutron flux in the vicinity of a reactor control rod . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/319471

Chicago Manual of Style (16th Edition):

Boettinger, William Leo, 1939-. “Neutron flux in the vicinity of a reactor control rod .” 1963. Masters Thesis, University of Arizona. Accessed June 17, 2019. http://hdl.handle.net/10150/319471.

MLA Handbook (7th Edition):

Boettinger, William Leo, 1939-. “Neutron flux in the vicinity of a reactor control rod .” 1963. Web. 17 Jun 2019.

Vancouver:

Boettinger, William Leo 1. Neutron flux in the vicinity of a reactor control rod . [Internet] [Masters thesis]. University of Arizona; 1963. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10150/319471.

Council of Science Editors:

Boettinger, William Leo 1. Neutron flux in the vicinity of a reactor control rod . [Masters Thesis]. University of Arizona; 1963. Available from: http://hdl.handle.net/10150/319471


University of Arizona

6. Hagen, Robert Norris, 1938-. The measurement of diffusion parameters in a low neutron flux .

Degree: 1963, University of Arizona

Subjects/Keywords: Neutron flux.

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APA (6th Edition):

Hagen, Robert Norris, 1. (1963). The measurement of diffusion parameters in a low neutron flux . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/319478

Chicago Manual of Style (16th Edition):

Hagen, Robert Norris, 1938-. “The measurement of diffusion parameters in a low neutron flux .” 1963. Masters Thesis, University of Arizona. Accessed June 17, 2019. http://hdl.handle.net/10150/319478.

MLA Handbook (7th Edition):

Hagen, Robert Norris, 1938-. “The measurement of diffusion parameters in a low neutron flux .” 1963. Web. 17 Jun 2019.

Vancouver:

Hagen, Robert Norris 1. The measurement of diffusion parameters in a low neutron flux . [Internet] [Masters thesis]. University of Arizona; 1963. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10150/319478.

Council of Science Editors:

Hagen, Robert Norris 1. The measurement of diffusion parameters in a low neutron flux . [Masters Thesis]. University of Arizona; 1963. Available from: http://hdl.handle.net/10150/319478


Stellenbosch University

7. Singo, Thifhelimbilu Daphney. Development of a high flux neutron radiation detection system for in-core temperature monitoring.

Degree: PhD, Physics, 2012, Stellenbosch University

 ENGLISH ABSTRACT: The objective of this research was to develop a neutron detection system that incorporates a mass spectrometer to measure high neutron flux in… (more)

Subjects/Keywords: Physics; Neutron physics; Neutron transport; High flux neutron detection systems

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APA (6th Edition):

Singo, T. D. (2012). Development of a high flux neutron radiation detection system for in-core temperature monitoring. (Doctoral Dissertation). Stellenbosch University. Retrieved from http://hdl.handle.net/10019.1/19999

Chicago Manual of Style (16th Edition):

Singo, Thifhelimbilu Daphney. “Development of a high flux neutron radiation detection system for in-core temperature monitoring.” 2012. Doctoral Dissertation, Stellenbosch University. Accessed June 17, 2019. http://hdl.handle.net/10019.1/19999.

MLA Handbook (7th Edition):

Singo, Thifhelimbilu Daphney. “Development of a high flux neutron radiation detection system for in-core temperature monitoring.” 2012. Web. 17 Jun 2019.

Vancouver:

Singo TD. Development of a high flux neutron radiation detection system for in-core temperature monitoring. [Internet] [Doctoral dissertation]. Stellenbosch University; 2012. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10019.1/19999.

Council of Science Editors:

Singo TD. Development of a high flux neutron radiation detection system for in-core temperature monitoring. [Doctoral Dissertation]. Stellenbosch University; 2012. Available from: http://hdl.handle.net/10019.1/19999


Georgia Tech

8. Abdul-Majid Alzaidi, Samir. New neutron detector using magnetically focused electrons for fast reactor neutron flux measurements.

Degree: PhD, Nuclear engineering, 1976, Georgia Tech

Subjects/Keywords: Neutron flux; Neutron counters

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APA (6th Edition):

Abdul-Majid Alzaidi, S. (1976). New neutron detector using magnetically focused electrons for fast reactor neutron flux measurements. (Doctoral Dissertation). Georgia Tech. Retrieved from http://hdl.handle.net/1853/30676

Chicago Manual of Style (16th Edition):

Abdul-Majid Alzaidi, Samir. “New neutron detector using magnetically focused electrons for fast reactor neutron flux measurements.” 1976. Doctoral Dissertation, Georgia Tech. Accessed June 17, 2019. http://hdl.handle.net/1853/30676.

MLA Handbook (7th Edition):

Abdul-Majid Alzaidi, Samir. “New neutron detector using magnetically focused electrons for fast reactor neutron flux measurements.” 1976. Web. 17 Jun 2019.

Vancouver:

Abdul-Majid Alzaidi S. New neutron detector using magnetically focused electrons for fast reactor neutron flux measurements. [Internet] [Doctoral dissertation]. Georgia Tech; 1976. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/1853/30676.

Council of Science Editors:

Abdul-Majid Alzaidi S. New neutron detector using magnetically focused electrons for fast reactor neutron flux measurements. [Doctoral Dissertation]. Georgia Tech; 1976. Available from: http://hdl.handle.net/1853/30676


University of Tennessee – Knoxville

9. Yue, Andrew T. Progress Toward a Redetermination of the Neutron Lifetime Through the Absolute Determination of Neutron Flux.

Degree: 2011, University of Tennessee – Knoxville

 The reported lifetime in an in-beam neutron lifetime experiment performed at NIST was tn = (886.3 ± 3.4) s. The largest source of uncertainty was… (more)

Subjects/Keywords: fundamental neutron physics; neutron lifetime; neutron flux; lithium cross section; beam lifetime experiment

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APA (6th Edition):

Yue, A. T. (2011). Progress Toward a Redetermination of the Neutron Lifetime Through the Absolute Determination of Neutron Flux. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/1243

Chicago Manual of Style (16th Edition):

Yue, Andrew T. “Progress Toward a Redetermination of the Neutron Lifetime Through the Absolute Determination of Neutron Flux.” 2011. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed June 17, 2019. https://trace.tennessee.edu/utk_graddiss/1243.

MLA Handbook (7th Edition):

Yue, Andrew T. “Progress Toward a Redetermination of the Neutron Lifetime Through the Absolute Determination of Neutron Flux.” 2011. Web. 17 Jun 2019.

Vancouver:

Yue AT. Progress Toward a Redetermination of the Neutron Lifetime Through the Absolute Determination of Neutron Flux. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2011. [cited 2019 Jun 17]. Available from: https://trace.tennessee.edu/utk_graddiss/1243.

Council of Science Editors:

Yue AT. Progress Toward a Redetermination of the Neutron Lifetime Through the Absolute Determination of Neutron Flux. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2011. Available from: https://trace.tennessee.edu/utk_graddiss/1243


University of Tennessee – Knoxville

10. Harrison, Thomas Jay. Methodology For Generating Simplified Cross Section Data Sets For Neutron Transport Calculations.

Degree: 2015, University of Tennessee – Knoxville

Neutron shielding problems involve radiation transport calculations over a wide range of energies. Fission neutrons have initial energy on the order of MeV, fusion neutrons… (more)

Subjects/Keywords: Neutron Cross Section; Neutron Shielding; Monte Carlo Methods; Neutron Flux Spectrum; Nuclear; Nuclear Engineering

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APA (6th Edition):

Harrison, T. J. (2015). Methodology For Generating Simplified Cross Section Data Sets For Neutron Transport Calculations. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/3583

Chicago Manual of Style (16th Edition):

Harrison, Thomas Jay. “Methodology For Generating Simplified Cross Section Data Sets For Neutron Transport Calculations.” 2015. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed June 17, 2019. https://trace.tennessee.edu/utk_graddiss/3583.

MLA Handbook (7th Edition):

Harrison, Thomas Jay. “Methodology For Generating Simplified Cross Section Data Sets For Neutron Transport Calculations.” 2015. Web. 17 Jun 2019.

Vancouver:

Harrison TJ. Methodology For Generating Simplified Cross Section Data Sets For Neutron Transport Calculations. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2015. [cited 2019 Jun 17]. Available from: https://trace.tennessee.edu/utk_graddiss/3583.

Council of Science Editors:

Harrison TJ. Methodology For Generating Simplified Cross Section Data Sets For Neutron Transport Calculations. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2015. Available from: https://trace.tennessee.edu/utk_graddiss/3583


University of Tennessee – Knoxville

11. Luciano, Nicholas Patrick. A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source.

Degree: MS, Nuclear Engineering, 2012, University of Tennessee – Knoxville

  The goal of this work was to develop a foil activation method to measure high-energy (∼1-100 MeV) neutron flux spectra at the Spallation Neutron(more)

Subjects/Keywords: High Energy; Flux; Neutron Spectrometry; Spallation Neutron Source; Gamma-ray Spectrometry; Foil; Nuclear; Nuclear Engineering

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APA (6th Edition):

Luciano, N. P. (2012). A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/1178

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

Chicago Manual of Style (16th Edition):

Luciano, Nicholas Patrick. “A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source.” 2012. Thesis, University of Tennessee – Knoxville. Accessed June 17, 2019. https://trace.tennessee.edu/utk_gradthes/1178.

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

MLA Handbook (7th Edition):

Luciano, Nicholas Patrick. “A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source.” 2012. Web. 17 Jun 2019.

Vancouver:

Luciano NP. A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source. [Internet] [Thesis]. University of Tennessee – Knoxville; 2012. [cited 2019 Jun 17]. Available from: https://trace.tennessee.edu/utk_gradthes/1178.

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

Council of Science Editors:

Luciano NP. A High-Energy Neutron Flux Spectra Measurement Method for the Spallation Neutron Source. [Thesis]. University of Tennessee – Knoxville; 2012. Available from: https://trace.tennessee.edu/utk_gradthes/1178

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


North-West University

12. Makgopa, Bessie Mmakgoto. Simulation of the irradiation behaviour of the PBMR fuel in the SAFARI-1 reactor / B.M. Makgopa .

Degree: 2009, North-West University

 Irradiation experiments for the pebble bed modular reactor PBMR fuel (coated fuel particles and pebble fuel) are planned at the South African First Atomic Reactor… (more)

Subjects/Keywords: MCNP5; Neutron flux; Neutron heating; OSCAR-3; Pebble; PBMR; Photon flux; Photon heating; Power distribution; SAFARI-1

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APA (6th Edition):

Makgopa, B. M. (2009). Simulation of the irradiation behaviour of the PBMR fuel in the SAFARI-1 reactor / B.M. Makgopa . (Thesis). North-West University. Retrieved from http://hdl.handle.net/10394/4030

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

Chicago Manual of Style (16th Edition):

Makgopa, Bessie Mmakgoto. “Simulation of the irradiation behaviour of the PBMR fuel in the SAFARI-1 reactor / B.M. Makgopa .” 2009. Thesis, North-West University. Accessed June 17, 2019. http://hdl.handle.net/10394/4030.

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

MLA Handbook (7th Edition):

Makgopa, Bessie Mmakgoto. “Simulation of the irradiation behaviour of the PBMR fuel in the SAFARI-1 reactor / B.M. Makgopa .” 2009. Web. 17 Jun 2019.

Vancouver:

Makgopa BM. Simulation of the irradiation behaviour of the PBMR fuel in the SAFARI-1 reactor / B.M. Makgopa . [Internet] [Thesis]. North-West University; 2009. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10394/4030.

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

Council of Science Editors:

Makgopa BM. Simulation of the irradiation behaviour of the PBMR fuel in the SAFARI-1 reactor / B.M. Makgopa . [Thesis]. North-West University; 2009. Available from: http://hdl.handle.net/10394/4030

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


The Ohio State University

13. Chenkovich, Robert Jeremy. Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes.

Degree: MS, Nuclear Engineering, 2008, The Ohio State University

 The objective of this work is to provide more accurate neutronic models of the OSU research reactor and also to provide a more complete characterization… (more)

Subjects/Keywords: Engineering; neutron flux; spectral analysis; spectral unfolding; activation; MCNP

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APA (6th Edition):

Chenkovich, R. J. (2008). Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes. (Masters Thesis). The Ohio State University. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=osu1206022975

Chicago Manual of Style (16th Edition):

Chenkovich, Robert Jeremy. “Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes.” 2008. Masters Thesis, The Ohio State University. Accessed June 17, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1206022975.

MLA Handbook (7th Edition):

Chenkovich, Robert Jeremy. “Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes.” 2008. Web. 17 Jun 2019.

Vancouver:

Chenkovich RJ. Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes. [Internet] [Masters thesis]. The Ohio State University; 2008. [cited 2019 Jun 17]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1206022975.

Council of Science Editors:

Chenkovich RJ. Refinement and Validation of Existing Computer Models of the OSU Research Reactor using Activation Analysis and Spectral Unfolding Codes. [Masters Thesis]. The Ohio State University; 2008. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=osu1206022975


Oregon State University

14. Nes, Razvan. An advanced nodal discretization for the quasi-diffusion low-order equations.

Degree: MS, Nuclear Engineering, 2002, Oregon State University

 The subject of this thesis is the development of a nodal discretization of the low-order quasi-diffusion (QDLO) equations for global reactor core calculations. The advantage… (more)

Subjects/Keywords: Neutron flux  – Mathematical models

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APA (6th Edition):

Nes, R. (2002). An advanced nodal discretization for the quasi-diffusion low-order equations. (Masters Thesis). Oregon State University. Retrieved from http://hdl.handle.net/1957/30335

Chicago Manual of Style (16th Edition):

Nes, Razvan. “An advanced nodal discretization for the quasi-diffusion low-order equations.” 2002. Masters Thesis, Oregon State University. Accessed June 17, 2019. http://hdl.handle.net/1957/30335.

MLA Handbook (7th Edition):

Nes, Razvan. “An advanced nodal discretization for the quasi-diffusion low-order equations.” 2002. Web. 17 Jun 2019.

Vancouver:

Nes R. An advanced nodal discretization for the quasi-diffusion low-order equations. [Internet] [Masters thesis]. Oregon State University; 2002. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/1957/30335.

Council of Science Editors:

Nes R. An advanced nodal discretization for the quasi-diffusion low-order equations. [Masters Thesis]. Oregon State University; 2002. Available from: http://hdl.handle.net/1957/30335


Delft University of Technology

15. Truax, J. Linking Laboratory and in situ Activation Analysis of Rock-forming Elements using a 14 MeV Neutron Source.

Degree: 1995, Delft University of Technology

Subjects/Keywords: neutron flux; activation spectrometry

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APA (6th Edition):

Truax, J. (1995). Linking Laboratory and in situ Activation Analysis of Rock-forming Elements using a 14 MeV Neutron Source. (Doctoral Dissertation). Delft University of Technology. Retrieved from http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6

Chicago Manual of Style (16th Edition):

Truax, J. “Linking Laboratory and in situ Activation Analysis of Rock-forming Elements using a 14 MeV Neutron Source.” 1995. Doctoral Dissertation, Delft University of Technology. Accessed June 17, 2019. http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6.

MLA Handbook (7th Edition):

Truax, J. “Linking Laboratory and in situ Activation Analysis of Rock-forming Elements using a 14 MeV Neutron Source.” 1995. Web. 17 Jun 2019.

Vancouver:

Truax J. Linking Laboratory and in situ Activation Analysis of Rock-forming Elements using a 14 MeV Neutron Source. [Internet] [Doctoral dissertation]. Delft University of Technology; 1995. [cited 2019 Jun 17]. Available from: http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6.

Council of Science Editors:

Truax J. Linking Laboratory and in situ Activation Analysis of Rock-forming Elements using a 14 MeV Neutron Source. [Doctoral Dissertation]. Delft University of Technology; 1995. Available from: http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; urn:NBN:nl:ui:24-uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6 ; http://resolver.tudelft.nl/uuid:cacc1a75-8aed-432a-b1cf-43de80ae7ec6


Colorado School of Mines

16. Alzaabi, Osama E. Benchmarking of neutron flux parameters at the USGS TRIGA reactor in Lakewood, Colorado.

Degree: PhD, Physics, 2018, Colorado School of Mines

 The USGS TRIGA Reactor (GSTR) located at the Denver Federal Center in Lakewood Colorado provides opportunities to Colorado School of Mines students to do experimental… (more)

Subjects/Keywords: Neutron flux parameters; USGS TRIGA reactor; TRIGA; GSTR

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APA (6th Edition):

Alzaabi, O. E. (2018). Benchmarking of neutron flux parameters at the USGS TRIGA reactor in Lakewood, Colorado. (Doctoral Dissertation). Colorado School of Mines. Retrieved from http://hdl.handle.net/11124/171976

Chicago Manual of Style (16th Edition):

Alzaabi, Osama E. “Benchmarking of neutron flux parameters at the USGS TRIGA reactor in Lakewood, Colorado.” 2018. Doctoral Dissertation, Colorado School of Mines. Accessed June 17, 2019. http://hdl.handle.net/11124/171976.

MLA Handbook (7th Edition):

Alzaabi, Osama E. “Benchmarking of neutron flux parameters at the USGS TRIGA reactor in Lakewood, Colorado.” 2018. Web. 17 Jun 2019.

Vancouver:

Alzaabi OE. Benchmarking of neutron flux parameters at the USGS TRIGA reactor in Lakewood, Colorado. [Internet] [Doctoral dissertation]. Colorado School of Mines; 2018. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/11124/171976.

Council of Science Editors:

Alzaabi OE. Benchmarking of neutron flux parameters at the USGS TRIGA reactor in Lakewood, Colorado. [Doctoral Dissertation]. Colorado School of Mines; 2018. Available from: http://hdl.handle.net/11124/171976


University of Texas – Austin

17. Graham, Joseph Turner. Characterization of neutron flux spectra for radiation effects studies.

Degree: Mechanical Engineering, 2011, University of Texas – Austin

 The effects of neutron displacement damage on materials are sensitive to neutron energy spectra. In controlled neutron damage experiments, a well characterized neutron flux spectrum… (more)

Subjects/Keywords: Neutron spectra; Flux characterization; Radiation effects; Methodologies; TRIGA

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APA (6th Edition):

Graham, J. T. (2011). Characterization of neutron flux spectra for radiation effects studies. (Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/21673

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

Chicago Manual of Style (16th Edition):

Graham, Joseph Turner. “Characterization of neutron flux spectra for radiation effects studies.” 2011. Thesis, University of Texas – Austin. Accessed June 17, 2019. http://hdl.handle.net/2152/21673.

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

MLA Handbook (7th Edition):

Graham, Joseph Turner. “Characterization of neutron flux spectra for radiation effects studies.” 2011. Web. 17 Jun 2019.

Vancouver:

Graham JT. Characterization of neutron flux spectra for radiation effects studies. [Internet] [Thesis]. University of Texas – Austin; 2011. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/2152/21673.

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

Council of Science Editors:

Graham JT. Characterization of neutron flux spectra for radiation effects studies. [Thesis]. University of Texas – Austin; 2011. Available from: http://hdl.handle.net/2152/21673

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


University of Arizona

18. Bernat, Steven Nicholas. Peaking factors in the University of Arizona research factor: core configuration, TEST-1 .

Degree: 1981, University of Arizona

Subjects/Keywords: Neutron flux.; Nuclear reactors.

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APA (6th Edition):

Bernat, S. N. (1981). Peaking factors in the University of Arizona research factor: core configuration, TEST-1 . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/626031

Chicago Manual of Style (16th Edition):

Bernat, Steven Nicholas. “Peaking factors in the University of Arizona research factor: core configuration, TEST-1 .” 1981. Masters Thesis, University of Arizona. Accessed June 17, 2019. http://hdl.handle.net/10150/626031.

MLA Handbook (7th Edition):

Bernat, Steven Nicholas. “Peaking factors in the University of Arizona research factor: core configuration, TEST-1 .” 1981. Web. 17 Jun 2019.

Vancouver:

Bernat SN. Peaking factors in the University of Arizona research factor: core configuration, TEST-1 . [Internet] [Masters thesis]. University of Arizona; 1981. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10150/626031.

Council of Science Editors:

Bernat SN. Peaking factors in the University of Arizona research factor: core configuration, TEST-1 . [Masters Thesis]. University of Arizona; 1981. Available from: http://hdl.handle.net/10150/626031


University of Arizona

19. Romesburg, H. Charles, 1938-. Absorption induced thermal neutron flux perturbations .

Degree: 1962, University of Arizona

Subjects/Keywords: Perturbation (Quantum dynamics); Neutron flux.

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APA (6th Edition):

Romesburg, H. Charles, 1. (1962). Absorption induced thermal neutron flux perturbations . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/319503

Chicago Manual of Style (16th Edition):

Romesburg, H. Charles, 1938-. “Absorption induced thermal neutron flux perturbations .” 1962. Masters Thesis, University of Arizona. Accessed June 17, 2019. http://hdl.handle.net/10150/319503.

MLA Handbook (7th Edition):

Romesburg, H. Charles, 1938-. “Absorption induced thermal neutron flux perturbations .” 1962. Web. 17 Jun 2019.

Vancouver:

Romesburg, H. Charles 1. Absorption induced thermal neutron flux perturbations . [Internet] [Masters thesis]. University of Arizona; 1962. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10150/319503.

Council of Science Editors:

Romesburg, H. Charles 1. Absorption induced thermal neutron flux perturbations . [Masters Thesis]. University of Arizona; 1962. Available from: http://hdl.handle.net/10150/319503


University of Arizona

20. Forehand, Harry MacDonald, 1941-. Time and space dependent neutron flux in an externally moderated spherical cavity .

Degree: 1973, University of Arizona

Subjects/Keywords: Fast neutrons.; Neutron flux.

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APA (6th Edition):

Forehand, Harry MacDonald, 1. (1973). Time and space dependent neutron flux in an externally moderated spherical cavity . (Masters Thesis). University of Arizona. Retrieved from http://hdl.handle.net/10150/554471

Chicago Manual of Style (16th Edition):

Forehand, Harry MacDonald, 1941-. “Time and space dependent neutron flux in an externally moderated spherical cavity .” 1973. Masters Thesis, University of Arizona. Accessed June 17, 2019. http://hdl.handle.net/10150/554471.

MLA Handbook (7th Edition):

Forehand, Harry MacDonald, 1941-. “Time and space dependent neutron flux in an externally moderated spherical cavity .” 1973. Web. 17 Jun 2019.

Vancouver:

Forehand, Harry MacDonald 1. Time and space dependent neutron flux in an externally moderated spherical cavity . [Internet] [Masters thesis]. University of Arizona; 1973. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10150/554471.

Council of Science Editors:

Forehand, Harry MacDonald 1. Time and space dependent neutron flux in an externally moderated spherical cavity . [Masters Thesis]. University of Arizona; 1973. Available from: http://hdl.handle.net/10150/554471

21. Mura, Luiz Ernesto Credidio. Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2011, University of São Paulo

Este trabalho apresenta os resultados dos valores de fluxo de nêutrons obtidos a partir da implantação de uma armadilha de nêutrons no núcleo do Reator… (more)

Subjects/Keywords: activation foils; armadilha de nêutrons; espectro de nêutrons; flux trap; fluxo de nêutrons; folhas de ativação; IPEN/MB-01 reactor; neutron flux; neutron spectrum; reator IPEN/MB-01

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APA (6th Edition):

Mura, L. E. C. (2011). Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16092011-135032/ ;

Chicago Manual of Style (16th Edition):

Mura, Luiz Ernesto Credidio. “Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01.” 2011. Masters Thesis, University of São Paulo. Accessed June 17, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16092011-135032/ ;.

MLA Handbook (7th Edition):

Mura, Luiz Ernesto Credidio. “Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01.” 2011. Web. 17 Jun 2019.

Vancouver:

Mura LEC. Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01. [Internet] [Masters thesis]. University of São Paulo; 2011. [cited 2019 Jun 17]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16092011-135032/ ;.

Council of Science Editors:

Mura LEC. Caracterização dos campos neutrônicos obtidos por meio de armadilha de nêutrons no interior do núcleo do reator nuclear IPEN/MB-01. [Masters Thesis]. University of São Paulo; 2011. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16092011-135032/ ;

22. Belkacemi, Lisa Thinhinane. Effet du flux d’irradiation sur la formation de nano-défauts dans des alliages ferritiques Fe-Ni et Fe-Mn : Irradiation flux effects on the formation of nanometric defects in Fe-Ni and Fe-Mn ferritic alloys.

Degree: Docteur es, Énergie nucléaire, 2018, Paris Saclay

La fragilisation des aciers de cuve des réacteurs nucléaires sous irradiation aux neutrons est le facteur limitant la durée de vie des centrales nucléaires françaises.… (more)

Subjects/Keywords: Effet de flux; Transférabilité ion-neutron; Alliages ferritiques; Transformation de phases; Microstructure; Flux effects; Ion-neutron transferability; Ferritic alloys; Phase transformation; Microstructure

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APA (6th Edition):

Belkacemi, L. T. (2018). Effet du flux d’irradiation sur la formation de nano-défauts dans des alliages ferritiques Fe-Ni et Fe-Mn : Irradiation flux effects on the formation of nanometric defects in Fe-Ni and Fe-Mn ferritic alloys. (Doctoral Dissertation). Paris Saclay. Retrieved from http://www.theses.fr/2018SACLS441

Chicago Manual of Style (16th Edition):

Belkacemi, Lisa Thinhinane. “Effet du flux d’irradiation sur la formation de nano-défauts dans des alliages ferritiques Fe-Ni et Fe-Mn : Irradiation flux effects on the formation of nanometric defects in Fe-Ni and Fe-Mn ferritic alloys.” 2018. Doctoral Dissertation, Paris Saclay. Accessed June 17, 2019. http://www.theses.fr/2018SACLS441.

MLA Handbook (7th Edition):

Belkacemi, Lisa Thinhinane. “Effet du flux d’irradiation sur la formation de nano-défauts dans des alliages ferritiques Fe-Ni et Fe-Mn : Irradiation flux effects on the formation of nanometric defects in Fe-Ni and Fe-Mn ferritic alloys.” 2018. Web. 17 Jun 2019.

Vancouver:

Belkacemi LT. Effet du flux d’irradiation sur la formation de nano-défauts dans des alliages ferritiques Fe-Ni et Fe-Mn : Irradiation flux effects on the formation of nanometric defects in Fe-Ni and Fe-Mn ferritic alloys. [Internet] [Doctoral dissertation]. Paris Saclay; 2018. [cited 2019 Jun 17]. Available from: http://www.theses.fr/2018SACLS441.

Council of Science Editors:

Belkacemi LT. Effet du flux d’irradiation sur la formation de nano-défauts dans des alliages ferritiques Fe-Ni et Fe-Mn : Irradiation flux effects on the formation of nanometric defects in Fe-Ni and Fe-Mn ferritic alloys. [Doctoral Dissertation]. Paris Saclay; 2018. Available from: http://www.theses.fr/2018SACLS441


University of Ontario Institute of Technology

23. Ahmad, Mohammad Mateen. Transmutation rates in the annulus gas of pressure tube water reactors.

Degree: 2011, University of Ontario Institute of Technology

 CANDU (CANada Deuterium Uranium) reactor utilizes Pressure Tube (PT) fuel channel design and heavy water as a coolant. Fuel channel annulus gas acts as an… (more)

Subjects/Keywords: Annulus gas; CANDU; Fuel channel; MCNP; Neutron flux; Pressure tube reactor; Supercritical water reactor; Transmutation

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APA (6th Edition):

Ahmad, M. M. (2011). Transmutation rates in the annulus gas of pressure tube water reactors. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/182

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

Chicago Manual of Style (16th Edition):

Ahmad, Mohammad Mateen. “Transmutation rates in the annulus gas of pressure tube water reactors.” 2011. Thesis, University of Ontario Institute of Technology. Accessed June 17, 2019. http://hdl.handle.net/10155/182.

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

MLA Handbook (7th Edition):

Ahmad, Mohammad Mateen. “Transmutation rates in the annulus gas of pressure tube water reactors.” 2011. Web. 17 Jun 2019.

Vancouver:

Ahmad MM. Transmutation rates in the annulus gas of pressure tube water reactors. [Internet] [Thesis]. University of Ontario Institute of Technology; 2011. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10155/182.

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

Council of Science Editors:

Ahmad MM. Transmutation rates in the annulus gas of pressure tube water reactors. [Thesis]. University of Ontario Institute of Technology; 2011. Available from: http://hdl.handle.net/10155/182

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

24. Duggan, Jerome L. The Angular Distribution and Total Flux of Neutrons Obtained from the Deuterium-Tritium Reaction.

Degree: 1956, North Texas State College

 Mono-energetic neutrons have been produced with the low-voltage Cockroft-Walton accelerator at North Texas State College using two different reactions. It is the purpose of this… (more)

Subjects/Keywords: neutron distribution; flux; Neutrons.; Deuterium.; Tritium.

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APA (6th Edition):

Duggan, J. L. (1956). The Angular Distribution and Total Flux of Neutrons Obtained from the Deuterium-Tritium Reaction. (Thesis). North Texas State College. Retrieved from https://digital.library.unt.edu/ark:/67531/metadc107901/

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

Chicago Manual of Style (16th Edition):

Duggan, Jerome L. “The Angular Distribution and Total Flux of Neutrons Obtained from the Deuterium-Tritium Reaction.” 1956. Thesis, North Texas State College. Accessed June 17, 2019. https://digital.library.unt.edu/ark:/67531/metadc107901/.

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

MLA Handbook (7th Edition):

Duggan, Jerome L. “The Angular Distribution and Total Flux of Neutrons Obtained from the Deuterium-Tritium Reaction.” 1956. Web. 17 Jun 2019.

Vancouver:

Duggan JL. The Angular Distribution and Total Flux of Neutrons Obtained from the Deuterium-Tritium Reaction. [Internet] [Thesis]. North Texas State College; 1956. [cited 2019 Jun 17]. Available from: https://digital.library.unt.edu/ark:/67531/metadc107901/.

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

Council of Science Editors:

Duggan JL. The Angular Distribution and Total Flux of Neutrons Obtained from the Deuterium-Tritium Reaction. [Thesis]. North Texas State College; 1956. Available from: https://digital.library.unt.edu/ark:/67531/metadc107901/

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

25. Santos, Diogo Feliciano dos. Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2015, University of São Paulo

Os experimentos realizados e apresentados nesta dissertação resultaram na caracterização neutrônica de núcleos na configuração cilíndrica com 30 varetas combustíveis de diâmetro com um espaço,… (more)

Subjects/Keywords: análise por ativação neutrônica; espectrometria gama; física de reator nuclear; fluxo de nêutrons; gamma spectrometry; neutron activation analysis; neutron flux; nuclear reaction rate; nuclear reactor physics; taxa de reação nuclear

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APA (6th Edition):

Santos, D. F. d. (2015). Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;

Chicago Manual of Style (16th Edition):

Santos, Diogo Feliciano dos. “Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01.” 2015. Masters Thesis, University of São Paulo. Accessed June 17, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;.

MLA Handbook (7th Edition):

Santos, Diogo Feliciano dos. “Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01.” 2015. Web. 17 Jun 2019.

Vancouver:

Santos DFd. Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01. [Internet] [Masters thesis]. University of São Paulo; 2015. [cited 2019 Jun 17]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;.

Council of Science Editors:

Santos DFd. Caracterização dos campos neutrônicos obtidos por meio de armadilhas de nêutrons a partir da utilização de água pesada (D2O) no interior do núcleo do reator nuclear IPEN/MB-01. [Masters Thesis]. University of São Paulo; 2015. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-22052015-135739/ ;


University of Notre Dame

26. Stephen J. Kuhn. Exploring Highly Anisotropic Vortex Lattices of Unconventional Superconductors Using Small Angle Neutron Scattering</h1>.

Degree: PhD, Physics, 2017, University of Notre Dame

  Superconductivity is described by its electronic and magnetic properties. One way to explore unconventional superconductors is to examine how these properties of superconductors behave… (more)

Subjects/Keywords: Polarized Neutron; SANS; KFe2As2; vortices; Unconventional Superconductors; Sr2RuO4; Small Angle Neutron Scattering; flux line lattice; PA-SANS; Iron-based superconductivity; vortex lattice; vortex; BaFe2As2

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APA (6th Edition):

Kuhn, S. J. (2017). Exploring Highly Anisotropic Vortex Lattices of Unconventional Superconductors Using Small Angle Neutron Scattering</h1>. (Doctoral Dissertation). University of Notre Dame. Retrieved from https://curate.nd.edu/show/f7623b61c3k

Chicago Manual of Style (16th Edition):

Kuhn, Stephen J.. “Exploring Highly Anisotropic Vortex Lattices of Unconventional Superconductors Using Small Angle Neutron Scattering</h1>.” 2017. Doctoral Dissertation, University of Notre Dame. Accessed June 17, 2019. https://curate.nd.edu/show/f7623b61c3k.

MLA Handbook (7th Edition):

Kuhn, Stephen J.. “Exploring Highly Anisotropic Vortex Lattices of Unconventional Superconductors Using Small Angle Neutron Scattering</h1>.” 2017. Web. 17 Jun 2019.

Vancouver:

Kuhn SJ. Exploring Highly Anisotropic Vortex Lattices of Unconventional Superconductors Using Small Angle Neutron Scattering</h1>. [Internet] [Doctoral dissertation]. University of Notre Dame; 2017. [cited 2019 Jun 17]. Available from: https://curate.nd.edu/show/f7623b61c3k.

Council of Science Editors:

Kuhn SJ. Exploring Highly Anisotropic Vortex Lattices of Unconventional Superconductors Using Small Angle Neutron Scattering</h1>. [Doctoral Dissertation]. University of Notre Dame; 2017. Available from: https://curate.nd.edu/show/f7623b61c3k


University of Manchester

27. Hussain, Asad. Synergistic Effects of Neutrons and Plasma on Materials in Fusion Reactors & Relaxation of Merging Magnetic Flux Ropes in Fusion and Solar Plasmas.

Degree: 2018, University of Manchester

 This thesis is submitted as requirement for the degree of Doctor of Philosophy. It comprises of essentially two parts. The first deals with materials in… (more)

Subjects/Keywords: Nuclear Fusion; Neutron transport; Magnetohydrdynamics; Material science; Plasma; Damage; Coronal heating; Flux ropes; Solar plasmas; Tokamak; Tungsten

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APA (6th Edition):

Hussain, A. (2018). Synergistic Effects of Neutrons and Plasma on Materials in Fusion Reactors & Relaxation of Merging Magnetic Flux Ropes in Fusion and Solar Plasmas. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:315044

Chicago Manual of Style (16th Edition):

Hussain, Asad. “Synergistic Effects of Neutrons and Plasma on Materials in Fusion Reactors & Relaxation of Merging Magnetic Flux Ropes in Fusion and Solar Plasmas.” 2018. Doctoral Dissertation, University of Manchester. Accessed June 17, 2019. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:315044.

MLA Handbook (7th Edition):

Hussain, Asad. “Synergistic Effects of Neutrons and Plasma on Materials in Fusion Reactors & Relaxation of Merging Magnetic Flux Ropes in Fusion and Solar Plasmas.” 2018. Web. 17 Jun 2019.

Vancouver:

Hussain A. Synergistic Effects of Neutrons and Plasma on Materials in Fusion Reactors & Relaxation of Merging Magnetic Flux Ropes in Fusion and Solar Plasmas. [Internet] [Doctoral dissertation]. University of Manchester; 2018. [cited 2019 Jun 17]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:315044.

Council of Science Editors:

Hussain A. Synergistic Effects of Neutrons and Plasma on Materials in Fusion Reactors & Relaxation of Merging Magnetic Flux Ropes in Fusion and Solar Plasmas. [Doctoral Dissertation]. University of Manchester; 2018. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:315044


University of Manchester

28. Hussain, Asad. Synergistic effects of neutrons and plasma on materials in fusion reactors & relaxation of merging magnetic flux ropes in fusion and solar plasmas.

Degree: PhD, 2018, University of Manchester

 This thesis comprises of essentially two parts. The first deals with materials in a fusion reactor and examines how neutron damage affects material in a… (more)

Subjects/Keywords: Tungsten; Solar plasmas; Flux ropes; Coronal heating; Damage; Tokamak; Material science; Magnetohydrdynamics; Neutron transport; Nuclear Fusion; Plasma

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APA (6th Edition):

Hussain, A. (2018). Synergistic effects of neutrons and plasma on materials in fusion reactors & relaxation of merging magnetic flux ropes in fusion and solar plasmas. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/synergistic-effects-of-neutrons-and-plasma-on-materials-in-fusion-reactors – relaxation-of-merging-magnetic-flux-ropes-in-fusion-and-solar-plasmas(9802cf3f-f977-460c-9e9d-314e9c0e8bd5).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.764577

Chicago Manual of Style (16th Edition):

Hussain, Asad. “Synergistic effects of neutrons and plasma on materials in fusion reactors & relaxation of merging magnetic flux ropes in fusion and solar plasmas.” 2018. Doctoral Dissertation, University of Manchester. Accessed June 17, 2019. https://www.research.manchester.ac.uk/portal/en/theses/synergistic-effects-of-neutrons-and-plasma-on-materials-in-fusion-reactors – relaxation-of-merging-magnetic-flux-ropes-in-fusion-and-solar-plasmas(9802cf3f-f977-460c-9e9d-314e9c0e8bd5).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.764577.

MLA Handbook (7th Edition):

Hussain, Asad. “Synergistic effects of neutrons and plasma on materials in fusion reactors & relaxation of merging magnetic flux ropes in fusion and solar plasmas.” 2018. Web. 17 Jun 2019.

Vancouver:

Hussain A. Synergistic effects of neutrons and plasma on materials in fusion reactors & relaxation of merging magnetic flux ropes in fusion and solar plasmas. [Internet] [Doctoral dissertation]. University of Manchester; 2018. [cited 2019 Jun 17]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/synergistic-effects-of-neutrons-and-plasma-on-materials-in-fusion-reactors – relaxation-of-merging-magnetic-flux-ropes-in-fusion-and-solar-plasmas(9802cf3f-f977-460c-9e9d-314e9c0e8bd5).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.764577.

Council of Science Editors:

Hussain A. Synergistic effects of neutrons and plasma on materials in fusion reactors & relaxation of merging magnetic flux ropes in fusion and solar plasmas. [Doctoral Dissertation]. University of Manchester; 2018. Available from: https://www.research.manchester.ac.uk/portal/en/theses/synergistic-effects-of-neutrons-and-plasma-on-materials-in-fusion-reactors – relaxation-of-merging-magnetic-flux-ropes-in-fusion-and-solar-plasmas(9802cf3f-f977-460c-9e9d-314e9c0e8bd5).html ; https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.764577


Virginia Tech

29. Teachman, John David. A nonlinear diffusion theory model for xenon-induced flux oscillations.

Degree: PhD, Nuclear Science and Engineering, 1981, Virginia Tech

Subjects/Keywords: LD5655.V856 1981.T422; Xenon; Neutron flux; Nuclear reactors

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APA (6th Edition):

Teachman, J. D. (1981). A nonlinear diffusion theory model for xenon-induced flux oscillations. (Doctoral Dissertation). Virginia Tech. Retrieved from http://hdl.handle.net/10919/76580

Chicago Manual of Style (16th Edition):

Teachman, John David. “A nonlinear diffusion theory model for xenon-induced flux oscillations.” 1981. Doctoral Dissertation, Virginia Tech. Accessed June 17, 2019. http://hdl.handle.net/10919/76580.

MLA Handbook (7th Edition):

Teachman, John David. “A nonlinear diffusion theory model for xenon-induced flux oscillations.” 1981. Web. 17 Jun 2019.

Vancouver:

Teachman JD. A nonlinear diffusion theory model for xenon-induced flux oscillations. [Internet] [Doctoral dissertation]. Virginia Tech; 1981. [cited 2019 Jun 17]. Available from: http://hdl.handle.net/10919/76580.

Council of Science Editors:

Teachman JD. A nonlinear diffusion theory model for xenon-induced flux oscillations. [Doctoral Dissertation]. Virginia Tech; 1981. Available from: http://hdl.handle.net/10919/76580


University of Notre Dame

30. Elizabeth R. Louden. Small-Angle Neutron Scattering Studies of Metastable Vortex Lattice States in MgB2</h1>.

Degree: PhD, Physics, 2018, University of Notre Dame

  Superconductivity remains a rich and active field over a century after its discovery. When exposed to a magnetic field, type II superconductors become threaded… (more)

Subjects/Keywords: Non-equilibrium Dynamics; Superconductivity; Vortex Lattice; Small-Angle Neutron Scattering; Flux-Line Lattice; Metastability; MgB2; Magnesium Diboride

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

APA (6th Edition):

Louden, E. R. (2018). Small-Angle Neutron Scattering Studies of Metastable Vortex Lattice States in MgB2</h1>. (Doctoral Dissertation). University of Notre Dame. Retrieved from https://curate.nd.edu/show/05741r69170

Chicago Manual of Style (16th Edition):

Louden, Elizabeth R.. “Small-Angle Neutron Scattering Studies of Metastable Vortex Lattice States in MgB2</h1>.” 2018. Doctoral Dissertation, University of Notre Dame. Accessed June 17, 2019. https://curate.nd.edu/show/05741r69170.

MLA Handbook (7th Edition):

Louden, Elizabeth R.. “Small-Angle Neutron Scattering Studies of Metastable Vortex Lattice States in MgB2</h1>.” 2018. Web. 17 Jun 2019.

Vancouver:

Louden ER. Small-Angle Neutron Scattering Studies of Metastable Vortex Lattice States in MgB2</h1>. [Internet] [Doctoral dissertation]. University of Notre Dame; 2018. [cited 2019 Jun 17]. Available from: https://curate.nd.edu/show/05741r69170.

Council of Science Editors:

Louden ER. Small-Angle Neutron Scattering Studies of Metastable Vortex Lattice States in MgB2</h1>. [Doctoral Dissertation]. University of Notre Dame; 2018. Available from: https://curate.nd.edu/show/05741r69170

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