Advanced search options

Advanced Search Options 🞨

Browse by author name (“Author name starts with…”).

Find ETDs with:

in
/  
in
/  
in
/  
in

Written in Published in Earliest date Latest date

Sorted by

Results per page:

Sorted by: relevance · author · university · dateNew search

You searched for subject:(MCNP). Showing records 1 – 30 of 147 total matches.

[1] [2] [3] [4] [5]

Search Limiters

Last 2 Years | English Only

Degrees

Levels

Languages

Country

▼ Search Limiters

1. Souza, Gregório Soares de. Projeto e implantação de melhorias na blindagem biológica da instalação para estudos em BNCT.

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

A técnica de captura de nêutrons em Boro é uma técnica promissora de tratamento de câncer, ela usa do alto LET das partículas provenientes da… (more)

Subjects/Keywords: blindagens; BNCT; BNCT; MCNP; MCNP; reactors; reatores

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Souza, G. S. d. (2011). Projeto e implantação de melhorias na blindagem biológica da instalação para estudos em BNCT. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-144054/ ;

Chicago Manual of Style (16th Edition):

Souza, Gregório Soares de. “Projeto e implantação de melhorias na blindagem biológica da instalação para estudos em BNCT.” 2011. Masters Thesis, University of São Paulo. Accessed September 25, 2020. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-144054/ ;.

MLA Handbook (7th Edition):

Souza, Gregório Soares de. “Projeto e implantação de melhorias na blindagem biológica da instalação para estudos em BNCT.” 2011. Web. 25 Sep 2020.

Vancouver:

Souza GSd. Projeto e implantação de melhorias na blindagem biológica da instalação para estudos em BNCT. [Internet] [Masters thesis]. University of São Paulo; 2011. [cited 2020 Sep 25]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-144054/ ;.

Council of Science Editors:

Souza GSd. Projeto e implantação de melhorias na blindagem biológica da instalação para estudos em BNCT. [Masters Thesis]. University of São Paulo; 2011. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-16062011-144054/ ;


Uppsala University

2. Dalborg, Erik. MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2.

Degree: Applied Nuclear Physics, 2013, Uppsala University

  In this report an MCNP (Monte Carlo N-Particle) model is described for the reactor vessel at Ringhals 2. The model is validated against the… (more)

Subjects/Keywords: MCNP; DPA; strålningsskador

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Dalborg, E. (2013). MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-199024

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):

Dalborg, Erik. “MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2.” 2013. Thesis, Uppsala University. Accessed September 25, 2020. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-199024.

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

MLA Handbook (7th Edition):

Dalborg, Erik. “MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2.” 2013. Web. 25 Sep 2020.

Vancouver:

Dalborg E. MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2. [Internet] [Thesis]. Uppsala University; 2013. [cited 2020 Sep 25]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-199024.

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

Council of Science Editors:

Dalborg E. MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2. [Thesis]. Uppsala University; 2013. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-199024

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


Georgia Tech

3. Benson, Bixler C. Feasibility of creating a neutron detector array for the detection of special nuclear materials.

Degree: MS, Mechanical Engineering, 2015, Georgia Tech

 The purpose of this research is to determine the feasibility of creating an energy-dependent neutron detector array that could be used to detect special nuclear… (more)

Subjects/Keywords: Neutron detection; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Benson, B. C. (2015). Feasibility of creating a neutron detector array for the detection of special nuclear materials. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/60397

Chicago Manual of Style (16th Edition):

Benson, Bixler C. “Feasibility of creating a neutron detector array for the detection of special nuclear materials.” 2015. Masters Thesis, Georgia Tech. Accessed September 25, 2020. http://hdl.handle.net/1853/60397.

MLA Handbook (7th Edition):

Benson, Bixler C. “Feasibility of creating a neutron detector array for the detection of special nuclear materials.” 2015. Web. 25 Sep 2020.

Vancouver:

Benson BC. Feasibility of creating a neutron detector array for the detection of special nuclear materials. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/1853/60397.

Council of Science Editors:

Benson BC. Feasibility of creating a neutron detector array for the detection of special nuclear materials. [Masters Thesis]. Georgia Tech; 2015. Available from: http://hdl.handle.net/1853/60397


University of Florida

4. Harkness, Allen Ira, III. Safeguards Approaches for Spent Nuclear Fuel in Dry Cask Storage.

Degree: PhD, Nuclear Engineering Sciences - Nuclear and Radiological Engineering, 2018, University of Florida

 Spent nuclear fuel is currently being stored in dry casks as an interim storage solution. Demand for this storage method has increased globally and the… (more)

Subjects/Keywords: mcnp  – neutron  – safeguards

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Harkness, Allen Ira, I. (2018). Safeguards Approaches for Spent Nuclear Fuel in Dry Cask Storage. (Doctoral Dissertation). University of Florida. Retrieved from https://ufdc.ufl.edu/UFE0052917

Chicago Manual of Style (16th Edition):

Harkness, Allen Ira, III. “Safeguards Approaches for Spent Nuclear Fuel in Dry Cask Storage.” 2018. Doctoral Dissertation, University of Florida. Accessed September 25, 2020. https://ufdc.ufl.edu/UFE0052917.

MLA Handbook (7th Edition):

Harkness, Allen Ira, III. “Safeguards Approaches for Spent Nuclear Fuel in Dry Cask Storage.” 2018. Web. 25 Sep 2020.

Vancouver:

Harkness, Allen Ira I. Safeguards Approaches for Spent Nuclear Fuel in Dry Cask Storage. [Internet] [Doctoral dissertation]. University of Florida; 2018. [cited 2020 Sep 25]. Available from: https://ufdc.ufl.edu/UFE0052917.

Council of Science Editors:

Harkness, Allen Ira I. Safeguards Approaches for Spent Nuclear Fuel in Dry Cask Storage. [Doctoral Dissertation]. University of Florida; 2018. Available from: https://ufdc.ufl.edu/UFE0052917


McMaster University

5. Ford, Wesley. Benchmarking of G4STORK for the Coolant Void Reactivity of the Super Critical Water Reactor Design.

Degree: MASc, 2016, McMaster University

The objectives of this thesis were the validation of G4STORK to use it for the investigation of the SCWR lattice cell. MCNP6 was chosen as… (more)

Subjects/Keywords: SCWR MCNP GEANT4 G4STORK Benchmark

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Ford, W. (2016). Benchmarking of G4STORK for the Coolant Void Reactivity of the Super Critical Water Reactor Design. (Masters Thesis). McMaster University. Retrieved from http://hdl.handle.net/11375/20027

Chicago Manual of Style (16th Edition):

Ford, Wesley. “Benchmarking of G4STORK for the Coolant Void Reactivity of the Super Critical Water Reactor Design.” 2016. Masters Thesis, McMaster University. Accessed September 25, 2020. http://hdl.handle.net/11375/20027.

MLA Handbook (7th Edition):

Ford, Wesley. “Benchmarking of G4STORK for the Coolant Void Reactivity of the Super Critical Water Reactor Design.” 2016. Web. 25 Sep 2020.

Vancouver:

Ford W. Benchmarking of G4STORK for the Coolant Void Reactivity of the Super Critical Water Reactor Design. [Internet] [Masters thesis]. McMaster University; 2016. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/11375/20027.

Council of Science Editors:

Ford W. Benchmarking of G4STORK for the Coolant Void Reactivity of the Super Critical Water Reactor Design. [Masters Thesis]. McMaster University; 2016. Available from: http://hdl.handle.net/11375/20027


University of Toledo

6. Zhang, Zhengdong. Quantitative Assessment of Radiation Dosimetry from a MammoSite balloon, FSD Applicator and a Newly Designed HDR Applicator for Treatment of GYN Cancers Using Monte Carlo Simulations.

Degree: PhD, Physics, 2009, University of Toledo

 This abstract contains three parts: 1) Computation of three dimensional attenuation presented by Mammosite Balloon in dosimetry of Partial Breast Irradiation. Current treatment planning systems… (more)

Subjects/Keywords: Physics; Mammosite; FSD; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Zhang, Z. (2009). Quantitative Assessment of Radiation Dosimetry from a MammoSite balloon, FSD Applicator and a Newly Designed HDR Applicator for Treatment of GYN Cancers Using Monte Carlo Simulations. (Doctoral Dissertation). University of Toledo. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=toledo1249334424

Chicago Manual of Style (16th Edition):

Zhang, Zhengdong. “Quantitative Assessment of Radiation Dosimetry from a MammoSite balloon, FSD Applicator and a Newly Designed HDR Applicator for Treatment of GYN Cancers Using Monte Carlo Simulations.” 2009. Doctoral Dissertation, University of Toledo. Accessed September 25, 2020. http://rave.ohiolink.edu/etdc/view?acc_num=toledo1249334424.

MLA Handbook (7th Edition):

Zhang, Zhengdong. “Quantitative Assessment of Radiation Dosimetry from a MammoSite balloon, FSD Applicator and a Newly Designed HDR Applicator for Treatment of GYN Cancers Using Monte Carlo Simulations.” 2009. Web. 25 Sep 2020.

Vancouver:

Zhang Z. Quantitative Assessment of Radiation Dosimetry from a MammoSite balloon, FSD Applicator and a Newly Designed HDR Applicator for Treatment of GYN Cancers Using Monte Carlo Simulations. [Internet] [Doctoral dissertation]. University of Toledo; 2009. [cited 2020 Sep 25]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=toledo1249334424.

Council of Science Editors:

Zhang Z. Quantitative Assessment of Radiation Dosimetry from a MammoSite balloon, FSD Applicator and a Newly Designed HDR Applicator for Treatment of GYN Cancers Using Monte Carlo Simulations. [Doctoral Dissertation]. University of Toledo; 2009. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=toledo1249334424

7. Fong, Kenneth B. Measuring the TG-43 Parameters of Iridium-192 using Monte Carlo-based Dosimetry.

Degree: MS, 2019, Worcester Polytechnic Institute

  Radioactive sources used in brachytherapy must be dosimetrically characterized prior to clinical use as defined the TG-43 protocol. In our previous project, Gafchromic film… (more)

Subjects/Keywords: MCNP; Dosimetry; Brachytherapy; Gafchromic film

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Fong, K. B. (2019). Measuring the TG-43 Parameters of Iridium-192 using Monte Carlo-based Dosimetry. (Thesis). Worcester Polytechnic Institute. Retrieved from etd-2341 ; https://digitalcommons.wpi.edu/etd-theses/1344

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):

Fong, Kenneth B. “Measuring the TG-43 Parameters of Iridium-192 using Monte Carlo-based Dosimetry.” 2019. Thesis, Worcester Polytechnic Institute. Accessed September 25, 2020. etd-2341 ; https://digitalcommons.wpi.edu/etd-theses/1344.

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

MLA Handbook (7th Edition):

Fong, Kenneth B. “Measuring the TG-43 Parameters of Iridium-192 using Monte Carlo-based Dosimetry.” 2019. Web. 25 Sep 2020.

Vancouver:

Fong KB. Measuring the TG-43 Parameters of Iridium-192 using Monte Carlo-based Dosimetry. [Internet] [Thesis]. Worcester Polytechnic Institute; 2019. [cited 2020 Sep 25]. Available from: etd-2341 ; https://digitalcommons.wpi.edu/etd-theses/1344.

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

Council of Science Editors:

Fong KB. Measuring the TG-43 Parameters of Iridium-192 using Monte Carlo-based Dosimetry. [Thesis]. Worcester Polytechnic Institute; 2019. Available from: etd-2341 ; https://digitalcommons.wpi.edu/etd-theses/1344

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

8. Poudel, Sashi. Variation in tissue correction factors for LiF, Al2O3 and Silicon Dosimeters as a function of tissue depth with comparison between intensity weighted mono-energetic photon and the poly-energetic photons used in brachytherapy and diagnostic radiology.

Degree: PhD, 2017, Worcester Polytechnic Institute

 "The MCNP6 radiation transport code was used to quantify changes in the absorbed dose tissue conversion factors for LiF, Al2O3, and silicon-based electronic dosimeters. While… (more)

Subjects/Keywords: Tissue Correction Factor; MCNP; Dosimeter

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Poudel, S. (2017). Variation in tissue correction factors for LiF, Al2O3 and Silicon Dosimeters as a function of tissue depth with comparison between intensity weighted mono-energetic photon and the poly-energetic photons used in brachytherapy and diagnostic radiology. (Doctoral Dissertation). Worcester Polytechnic Institute. Retrieved from etd-101417-143952 ; https://digitalcommons.wpi.edu/etd-dissertations/487

Chicago Manual of Style (16th Edition):

Poudel, Sashi. “Variation in tissue correction factors for LiF, Al2O3 and Silicon Dosimeters as a function of tissue depth with comparison between intensity weighted mono-energetic photon and the poly-energetic photons used in brachytherapy and diagnostic radiology.” 2017. Doctoral Dissertation, Worcester Polytechnic Institute. Accessed September 25, 2020. etd-101417-143952 ; https://digitalcommons.wpi.edu/etd-dissertations/487.

MLA Handbook (7th Edition):

Poudel, Sashi. “Variation in tissue correction factors for LiF, Al2O3 and Silicon Dosimeters as a function of tissue depth with comparison between intensity weighted mono-energetic photon and the poly-energetic photons used in brachytherapy and diagnostic radiology.” 2017. Web. 25 Sep 2020.

Vancouver:

Poudel S. Variation in tissue correction factors for LiF, Al2O3 and Silicon Dosimeters as a function of tissue depth with comparison between intensity weighted mono-energetic photon and the poly-energetic photons used in brachytherapy and diagnostic radiology. [Internet] [Doctoral dissertation]. Worcester Polytechnic Institute; 2017. [cited 2020 Sep 25]. Available from: etd-101417-143952 ; https://digitalcommons.wpi.edu/etd-dissertations/487.

Council of Science Editors:

Poudel S. Variation in tissue correction factors for LiF, Al2O3 and Silicon Dosimeters as a function of tissue depth with comparison between intensity weighted mono-energetic photon and the poly-energetic photons used in brachytherapy and diagnostic radiology. [Doctoral Dissertation]. Worcester Polytechnic Institute; 2017. Available from: etd-101417-143952 ; https://digitalcommons.wpi.edu/etd-dissertations/487


Texas A&M University

9. Holzaepfel, Aaron J. High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite.

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

 The study of thermal radiative transfer in the high energy density regime is important to the National Nuclear Security Administration, and experiments are an important… (more)

Subjects/Keywords: Radiation Transport; Uncertainty Quantification; Deterministic Transport; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Holzaepfel, A. J. (2016). High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/157938

Chicago Manual of Style (16th Edition):

Holzaepfel, Aaron J. “High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite.” 2016. Masters Thesis, Texas A&M University. Accessed September 25, 2020. http://hdl.handle.net/1969.1/157938.

MLA Handbook (7th Edition):

Holzaepfel, Aaron J. “High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite.” 2016. Web. 25 Sep 2020.

Vancouver:

Holzaepfel AJ. High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite. [Internet] [Masters thesis]. Texas A&M University; 2016. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/1969.1/157938.

Council of Science Editors:

Holzaepfel AJ. High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite. [Masters Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/157938


Texas A&M University

10. Quick, Costner Mclaine. Development of an Alternative to the Helium-3 Based Active Well Coincidence Counter with Boron Coated Straws.

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

 An active well coincidence counter (AWCC) is used for Nondestructive Assay (NDA) of special nuclear material. This counter was developed for the International Atomic Energy… (more)

Subjects/Keywords: Helium-3; Active Well Coincidence Counter; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Quick, C. M. (2018). Development of an Alternative to the Helium-3 Based Active Well Coincidence Counter with Boron Coated Straws. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173822

Chicago Manual of Style (16th Edition):

Quick, Costner Mclaine. “Development of an Alternative to the Helium-3 Based Active Well Coincidence Counter with Boron Coated Straws.” 2018. Masters Thesis, Texas A&M University. Accessed September 25, 2020. http://hdl.handle.net/1969.1/173822.

MLA Handbook (7th Edition):

Quick, Costner Mclaine. “Development of an Alternative to the Helium-3 Based Active Well Coincidence Counter with Boron Coated Straws.” 2018. Web. 25 Sep 2020.

Vancouver:

Quick CM. Development of an Alternative to the Helium-3 Based Active Well Coincidence Counter with Boron Coated Straws. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/1969.1/173822.

Council of Science Editors:

Quick CM. Development of an Alternative to the Helium-3 Based Active Well Coincidence Counter with Boron Coated Straws. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173822


Texas A&M University

11. Joe Justina, -. Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal.

Degree: MS, Nuclear Engineering, 2012, Texas A&M University

 A large radiological accident will result in the contamination of surrounding people, animal, vegetation etc. In such a situation assessing of the level of contamination… (more)

Subjects/Keywords: Portal monitor; Optimal detector Configuration; MCNP; MDA

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Joe Justina, -. (2012). Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517

Chicago Manual of Style (16th Edition):

Joe Justina, -. “Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal.” 2012. Masters Thesis, Texas A&M University. Accessed September 25, 2020. http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517.

MLA Handbook (7th Edition):

Joe Justina, -. “Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal.” 2012. Web. 25 Sep 2020.

Vancouver:

Joe Justina -. Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517.

Council of Science Editors:

Joe Justina -. Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517

12. Henrique Ribeiro Peixoto, Paulo. Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos .

Degree: 2008, Universidade Federal de Pernambuco

 Ratos são comumente utilizados como modelos experimentais em testes pre-clinicos na area de medicina nuclear. Torna-se, pois, de grande importância a realização de estimativas precisas… (more)

Subjects/Keywords: Modelo tomografico; Dosimetria; Rato; Fração absorvida; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Henrique Ribeiro Peixoto, P. (2008). Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos . (Thesis). Universidade Federal de Pernambuco. Retrieved from http://repositorio.ufpe.br/handle/123456789/9365

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):

Henrique Ribeiro Peixoto, Paulo. “Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos .” 2008. Thesis, Universidade Federal de Pernambuco. Accessed September 25, 2020. http://repositorio.ufpe.br/handle/123456789/9365.

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

MLA Handbook (7th Edition):

Henrique Ribeiro Peixoto, Paulo. “Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos .” 2008. Web. 25 Sep 2020.

Vancouver:

Henrique Ribeiro Peixoto P. Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos . [Internet] [Thesis]. Universidade Federal de Pernambuco; 2008. [cited 2020 Sep 25]. Available from: http://repositorio.ufpe.br/handle/123456789/9365.

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

Council of Science Editors:

Henrique Ribeiro Peixoto P. Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos . [Thesis]. Universidade Federal de Pernambuco; 2008. Available from: http://repositorio.ufpe.br/handle/123456789/9365

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

13. Sacay, Edna Monika. Monte Carlo calculated efficiency curve investigation for the Ontario Power Generation moving bed whole body counter.

Degree: 2014, University of Ontario Institute of Technology

 Accurate dose reporting for facilities regulated by the Canadian Nuclear Safety Commission (CNSC) rely on the proper calibration of their whole body counters (WBCs) for… (more)

Subjects/Keywords: Efficiency calibration; HPGe detector; MCNP; Photons; Phantom

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Sacay, E. M. (2014). Monte Carlo calculated efficiency curve investigation for the Ontario Power Generation moving bed whole body counter. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/484

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):

Sacay, Edna Monika. “Monte Carlo calculated efficiency curve investigation for the Ontario Power Generation moving bed whole body counter.” 2014. Thesis, University of Ontario Institute of Technology. Accessed September 25, 2020. http://hdl.handle.net/10155/484.

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

MLA Handbook (7th Edition):

Sacay, Edna Monika. “Monte Carlo calculated efficiency curve investigation for the Ontario Power Generation moving bed whole body counter.” 2014. Web. 25 Sep 2020.

Vancouver:

Sacay EM. Monte Carlo calculated efficiency curve investigation for the Ontario Power Generation moving bed whole body counter. [Internet] [Thesis]. University of Ontario Institute of Technology; 2014. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/10155/484.

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

Council of Science Editors:

Sacay EM. Monte Carlo calculated efficiency curve investigation for the Ontario Power Generation moving bed whole body counter. [Thesis]. University of Ontario Institute of Technology; 2014. Available from: http://hdl.handle.net/10155/484

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

14. Graham, Hannah Robyn. Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter.

Degree: 2015, University of Ontario Institute of Technology

 In order to be able to qualify and quantify radiation exposure in terms of dose, a Fastscan whole body counter must be calibrated correctly. Current… (more)

Subjects/Keywords: Monte Carlo; MCNP; Efficiency; Fastscan; BOMAB

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Graham, H. R. (2015). Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/556

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, Hannah Robyn. “Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter.” 2015. Thesis, University of Ontario Institute of Technology. Accessed September 25, 2020. http://hdl.handle.net/10155/556.

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

MLA Handbook (7th Edition):

Graham, Hannah Robyn. “Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter.” 2015. Web. 25 Sep 2020.

Vancouver:

Graham HR. Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter. [Internet] [Thesis]. University of Ontario Institute of Technology; 2015. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/10155/556.

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

Council of Science Editors:

Graham HR. Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter. [Thesis]. University of Ontario Institute of Technology; 2015. Available from: http://hdl.handle.net/10155/556

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


University of Tennessee – Knoxville

15. Cooper, Michael. Semi-Empirical Modeling and Implementation of Hybrid K-Edge Densitometry for Pyroprocessing Applications.

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

 The United States is currently looking at options for handling of spent nuclear fuel.Currently, there are ≈ 70, 000 metric tons of spent fuel in… (more)

Subjects/Keywords: MCNP; KED; XRF; Pyroprocessing; HKED; Safeguards

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Cooper, M. (2019). Semi-Empirical Modeling and Implementation of Hybrid K-Edge Densitometry for Pyroprocessing Applications. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/5526

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):

Cooper, Michael. “Semi-Empirical Modeling and Implementation of Hybrid K-Edge Densitometry for Pyroprocessing Applications.” 2019. Thesis, University of Tennessee – Knoxville. Accessed September 25, 2020. https://trace.tennessee.edu/utk_gradthes/5526.

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

MLA Handbook (7th Edition):

Cooper, Michael. “Semi-Empirical Modeling and Implementation of Hybrid K-Edge Densitometry for Pyroprocessing Applications.” 2019. Web. 25 Sep 2020.

Vancouver:

Cooper M. Semi-Empirical Modeling and Implementation of Hybrid K-Edge Densitometry for Pyroprocessing Applications. [Internet] [Thesis]. University of Tennessee – Knoxville; 2019. [cited 2020 Sep 25]. Available from: https://trace.tennessee.edu/utk_gradthes/5526.

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

Council of Science Editors:

Cooper M. Semi-Empirical Modeling and Implementation of Hybrid K-Edge Densitometry for Pyroprocessing Applications. [Thesis]. University of Tennessee – Knoxville; 2019. Available from: https://trace.tennessee.edu/utk_gradthes/5526

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


Colorado State University

16. Adams, David Wright. Comparison of MCNP modeling against empirical data for the measurement of gamma fields due to actinide oxides in a glovebox.

Degree: MS(M.S.), Environmental and Radiological Health Sciences, 2012, Colorado State University

 Los Alamos National Laboratory (LANL) is a facility that conducts research in the fields of global security, astrophysics, nuclear energy, and materials science. At Technical… (more)

Subjects/Keywords: actinide oxide; Monte Carlo; MCNP; glovebox; dosimetry

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Adams, D. W. (2012). Comparison of MCNP modeling against empirical data for the measurement of gamma fields due to actinide oxides in a glovebox. (Masters Thesis). Colorado State University. Retrieved from http://hdl.handle.net/10217/72373

Chicago Manual of Style (16th Edition):

Adams, David Wright. “Comparison of MCNP modeling against empirical data for the measurement of gamma fields due to actinide oxides in a glovebox.” 2012. Masters Thesis, Colorado State University. Accessed September 25, 2020. http://hdl.handle.net/10217/72373.

MLA Handbook (7th Edition):

Adams, David Wright. “Comparison of MCNP modeling against empirical data for the measurement of gamma fields due to actinide oxides in a glovebox.” 2012. Web. 25 Sep 2020.

Vancouver:

Adams DW. Comparison of MCNP modeling against empirical data for the measurement of gamma fields due to actinide oxides in a glovebox. [Internet] [Masters thesis]. Colorado State University; 2012. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/10217/72373.

Council of Science Editors:

Adams DW. Comparison of MCNP modeling against empirical data for the measurement of gamma fields due to actinide oxides in a glovebox. [Masters Thesis]. Colorado State University; 2012. Available from: http://hdl.handle.net/10217/72373


University of Cincinnati

17. Corder, Tyler J. Monte Carlo simulation of the photon flux at the center of a concentric ring of 60Co sources in the University of Cincinnati pool irradiator.

Degree: MS, Engineering and Applied Science: Nuclear and Radiological Engineering, 2019, University of Cincinnati

 This research will mathematically simulate the gamma radiation received by samples irradiated in the Cobalt-60 irradiation pool at the University of Cincinnati to provide more… (more)

Subjects/Keywords: Nuclear Engineering; MCNP; Cobalt-60; Irradiator; SDEF

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Corder, T. J. (2019). Monte Carlo simulation of the photon flux at the center of a concentric ring of 60Co sources in the University of Cincinnati pool irradiator. (Masters Thesis). University of Cincinnati. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=ucin1563274116720436

Chicago Manual of Style (16th Edition):

Corder, Tyler J. “Monte Carlo simulation of the photon flux at the center of a concentric ring of 60Co sources in the University of Cincinnati pool irradiator.” 2019. Masters Thesis, University of Cincinnati. Accessed September 25, 2020. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1563274116720436.

MLA Handbook (7th Edition):

Corder, Tyler J. “Monte Carlo simulation of the photon flux at the center of a concentric ring of 60Co sources in the University of Cincinnati pool irradiator.” 2019. Web. 25 Sep 2020.

Vancouver:

Corder TJ. Monte Carlo simulation of the photon flux at the center of a concentric ring of 60Co sources in the University of Cincinnati pool irradiator. [Internet] [Masters thesis]. University of Cincinnati; 2019. [cited 2020 Sep 25]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=ucin1563274116720436.

Council of Science Editors:

Corder TJ. Monte Carlo simulation of the photon flux at the center of a concentric ring of 60Co sources in the University of Cincinnati pool irradiator. [Masters Thesis]. University of Cincinnati; 2019. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=ucin1563274116720436


University of Ontario Institute of Technology

18. Gilbert, Jordan. Simulation of in-core dose rates for an offline CANDU reactor.

Degree: 2016, University of Ontario Institute of Technology

 This thesis describes the development of a Monte Carlo simulation to predict the dose rates that will be encountered by a novel robotic inspection system… (more)

Subjects/Keywords: MCNP; CANDU; Fuel channel; Inspections; Dose

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Gilbert, J. (2016). Simulation of in-core dose rates for an offline CANDU reactor. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/642

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):

Gilbert, Jordan. “Simulation of in-core dose rates for an offline CANDU reactor.” 2016. Thesis, University of Ontario Institute of Technology. Accessed September 25, 2020. http://hdl.handle.net/10155/642.

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

MLA Handbook (7th Edition):

Gilbert, Jordan. “Simulation of in-core dose rates for an offline CANDU reactor.” 2016. Web. 25 Sep 2020.

Vancouver:

Gilbert J. Simulation of in-core dose rates for an offline CANDU reactor. [Internet] [Thesis]. University of Ontario Institute of Technology; 2016. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/10155/642.

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

Council of Science Editors:

Gilbert J. Simulation of in-core dose rates for an offline CANDU reactor. [Thesis]. University of Ontario Institute of Technology; 2016. Available from: http://hdl.handle.net/10155/642

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


University of Florida

19. Sandler, Gabriel A. Verification and Validation of Atmospheric Transport Models Using the University of Florida Training Reactor.

Degree: PhD, Nuclear Engineering Sciences - Nuclear and Radiological Engineering, 2019, University of Florida

 The University of Florida Training Reactor (UFTR) is a 100-kW ARGONAUT type reactor with a unique design such that a large volume of air passes… (more)

Subjects/Keywords: aermod  – atmospheric  – ctbt  – flexpart  – gaussian  – mcnp

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Sandler, G. A. (2019). Verification and Validation of Atmospheric Transport Models Using the University of Florida Training Reactor. (Doctoral Dissertation). University of Florida. Retrieved from https://ufdc.ufl.edu/UFE0055600

Chicago Manual of Style (16th Edition):

Sandler, Gabriel A. “Verification and Validation of Atmospheric Transport Models Using the University of Florida Training Reactor.” 2019. Doctoral Dissertation, University of Florida. Accessed September 25, 2020. https://ufdc.ufl.edu/UFE0055600.

MLA Handbook (7th Edition):

Sandler, Gabriel A. “Verification and Validation of Atmospheric Transport Models Using the University of Florida Training Reactor.” 2019. Web. 25 Sep 2020.

Vancouver:

Sandler GA. Verification and Validation of Atmospheric Transport Models Using the University of Florida Training Reactor. [Internet] [Doctoral dissertation]. University of Florida; 2019. [cited 2020 Sep 25]. Available from: https://ufdc.ufl.edu/UFE0055600.

Council of Science Editors:

Sandler GA. Verification and Validation of Atmospheric Transport Models Using the University of Florida Training Reactor. [Doctoral Dissertation]. University of Florida; 2019. Available from: https://ufdc.ufl.edu/UFE0055600


University of Tennessee – Knoxville

20. Wilkerson, Robert Blake. A Bayesian Approach to Aerial Localization of Radioactive Sources.

Degree: MS, Nuclear Engineering, 2016, University of Tennessee – Knoxville

  Securing nuclear material has become an important area for the safety of the U.S. and other countries. Within nuclear security, there is a potential… (more)

Subjects/Keywords: gamma; radiation; search; Bayes; MCNP; Nuclear Engineering

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Wilkerson, R. B. (2016). A Bayesian Approach to Aerial Localization of Radioactive Sources. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/4273

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):

Wilkerson, Robert Blake. “A Bayesian Approach to Aerial Localization of Radioactive Sources.” 2016. Thesis, University of Tennessee – Knoxville. Accessed September 25, 2020. https://trace.tennessee.edu/utk_gradthes/4273.

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

MLA Handbook (7th Edition):

Wilkerson, Robert Blake. “A Bayesian Approach to Aerial Localization of Radioactive Sources.” 2016. Web. 25 Sep 2020.

Vancouver:

Wilkerson RB. A Bayesian Approach to Aerial Localization of Radioactive Sources. [Internet] [Thesis]. University of Tennessee – Knoxville; 2016. [cited 2020 Sep 25]. Available from: https://trace.tennessee.edu/utk_gradthes/4273.

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

Council of Science Editors:

Wilkerson RB. A Bayesian Approach to Aerial Localization of Radioactive Sources. [Thesis]. University of Tennessee – Knoxville; 2016. Available from: https://trace.tennessee.edu/utk_gradthes/4273

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

21. Antunes, Paula Cristina Guimarães. Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2010, University of São Paulo

A radioterapia é uma modalidade terapêutica que utiliza radiações ionizantes para erradicar as células neoplásicas do organismo humano. Um dos requisitos para o sucesso desta… (more)

Subjects/Keywords: algoritmo de segmentação; dosimetria de pele; MCNP; MCNP; objeto simulador segmentado; radioterapia; radiotherapy; skin dosimetry

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Antunes, P. C. G. (2010). Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12082011-164705/ ;

Chicago Manual of Style (16th Edition):

Antunes, Paula Cristina Guimarães. “Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele.” 2010. Masters Thesis, University of São Paulo. Accessed September 25, 2020. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12082011-164705/ ;.

MLA Handbook (7th Edition):

Antunes, Paula Cristina Guimarães. “Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele.” 2010. Web. 25 Sep 2020.

Vancouver:

Antunes PCG. Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele. [Internet] [Masters thesis]. University of São Paulo; 2010. [cited 2020 Sep 25]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12082011-164705/ ;.

Council of Science Editors:

Antunes PCG. Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele. [Masters Thesis]. University of São Paulo; 2010. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-12082011-164705/ ;

22. Possani, Rafael Guedes. Re-engenharia do software SCMS para uma linguagem orientada a objetos (Java) para uso em construções de phantoms segmentados.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2012, University of São Paulo

Metodologias recentes de planejamento dependem fortemente de imagens de tomografia computadorizada e a tendência é que os procedimentos de dosimetria interna na terapia usando medicina… (more)

Subjects/Keywords: MCNP; MCNP; medicina nuclear; Monte Carlo; Monte Carlo; nuclear medicine; SCMS; SCMS; terapia; therapy

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Possani, R. G. (2012). Re-engenharia do software SCMS para uma linguagem orientada a objetos (Java) para uso em construções de phantoms segmentados. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-04062012-152752/ ;

Chicago Manual of Style (16th Edition):

Possani, Rafael Guedes. “Re-engenharia do software SCMS para uma linguagem orientada a objetos (Java) para uso em construções de phantoms segmentados.” 2012. Masters Thesis, University of São Paulo. Accessed September 25, 2020. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-04062012-152752/ ;.

MLA Handbook (7th Edition):

Possani, Rafael Guedes. “Re-engenharia do software SCMS para uma linguagem orientada a objetos (Java) para uso em construções de phantoms segmentados.” 2012. Web. 25 Sep 2020.

Vancouver:

Possani RG. Re-engenharia do software SCMS para uma linguagem orientada a objetos (Java) para uso em construções de phantoms segmentados. [Internet] [Masters thesis]. University of São Paulo; 2012. [cited 2020 Sep 25]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-04062012-152752/ ;.

Council of Science Editors:

Possani RG. Re-engenharia do software SCMS para uma linguagem orientada a objetos (Java) para uso em construções de phantoms segmentados. [Masters Thesis]. University of São Paulo; 2012. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-04062012-152752/ ;

23. Tada, Ariane. Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2010, University of São Paulo

As lesões dermatológicas submetidas à terapia com fontes de radiação podem apresentar diferentes padrões de malignidade. Os tumores de pele mais comumente encontrados nos serviços… (more)

Subjects/Keywords: dosimetria; dosimetry; fontes de radiação; lesões de pele; MCNP; MCNP; radiation sources; radioterapia; radiotherapy; skin lesions

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Tada, A. (2010). Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02082011-125808/ ;

Chicago Manual of Style (16th Edition):

Tada, Ariane. “Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas.” 2010. Masters Thesis, University of São Paulo. Accessed September 25, 2020. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02082011-125808/ ;.

MLA Handbook (7th Edition):

Tada, Ariane. “Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas.” 2010. Web. 25 Sep 2020.

Vancouver:

Tada A. Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas. [Internet] [Masters thesis]. University of São Paulo; 2010. [cited 2020 Sep 25]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02082011-125808/ ;.

Council of Science Editors:

Tada A. Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas. [Masters Thesis]. University of São Paulo; 2010. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02082011-125808/ ;

24. Fonseca, Gabriel Paiva. Projeto e construção de placas espalhadoras e degradadoras de energia para  uso em radioterapia com feixes de elétrons para doenças de pele.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2010, University of São Paulo

Há diversas enfermidades radiossensíveis epidermotrópicas, como a micose fungóide e a síndrome de Sézary, neoplasias cutâneas originadas de linfócitos do tipo T, que apresentam grande… (more)

Subjects/Keywords: coetaneous neoplasics; linfoma cutâneo; MCNP; MCNP; método de Monte Carlo; Monte Carlo method; radioterapia; radiotherapy; TSET; TSET

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Fonseca, G. P. (2010). Projeto e construção de placas espalhadoras e degradadoras de energia para  uso em radioterapia com feixes de elétrons para doenças de pele. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-10082011-095658/ ;

Chicago Manual of Style (16th Edition):

Fonseca, Gabriel Paiva. “Projeto e construção de placas espalhadoras e degradadoras de energia para  uso em radioterapia com feixes de elétrons para doenças de pele.” 2010. Masters Thesis, University of São Paulo. Accessed September 25, 2020. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-10082011-095658/ ;.

MLA Handbook (7th Edition):

Fonseca, Gabriel Paiva. “Projeto e construção de placas espalhadoras e degradadoras de energia para  uso em radioterapia com feixes de elétrons para doenças de pele.” 2010. Web. 25 Sep 2020.

Vancouver:

Fonseca GP. Projeto e construção de placas espalhadoras e degradadoras de energia para  uso em radioterapia com feixes de elétrons para doenças de pele. [Internet] [Masters thesis]. University of São Paulo; 2010. [cited 2020 Sep 25]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-10082011-095658/ ;.

Council of Science Editors:

Fonseca GP. Projeto e construção de placas espalhadoras e degradadoras de energia para  uso em radioterapia com feixes de elétrons para doenças de pele. [Masters Thesis]. University of São Paulo; 2010. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-10082011-095658/ ;

25. Onillon, Anthony. Prédiction des taux de fission des coeurs de Chooz et estimation des incertitudes associées dans le cadre de l'expérience Double Chooz : Estimation of the Chooz cores fission rates and associated errors in the framework of the Double Chooz experiment.

Degree: Docteur es, Constituants élémentaires et physique théorique, 2014, Nantes, Ecole des Mines

Double Chooz est une expérience dédiée à la mesure de l'angle de mélange θ₁₃ caractérisant le phénomène d’oscillation des neutrinos. Elle consiste en l’installation de… (more)

Subjects/Keywords: Double Chooz; Oscillation neutrino; Simulation réacteur; MURE; MCNP; Double Chooz; Neutrino oscillation; Reactor simulation; MURE; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Onillon, A. (2014). Prédiction des taux de fission des coeurs de Chooz et estimation des incertitudes associées dans le cadre de l'expérience Double Chooz : Estimation of the Chooz cores fission rates and associated errors in the framework of the Double Chooz experiment. (Doctoral Dissertation). Nantes, Ecole des Mines. Retrieved from http://www.theses.fr/2014EMNA0116

Chicago Manual of Style (16th Edition):

Onillon, Anthony. “Prédiction des taux de fission des coeurs de Chooz et estimation des incertitudes associées dans le cadre de l'expérience Double Chooz : Estimation of the Chooz cores fission rates and associated errors in the framework of the Double Chooz experiment.” 2014. Doctoral Dissertation, Nantes, Ecole des Mines. Accessed September 25, 2020. http://www.theses.fr/2014EMNA0116.

MLA Handbook (7th Edition):

Onillon, Anthony. “Prédiction des taux de fission des coeurs de Chooz et estimation des incertitudes associées dans le cadre de l'expérience Double Chooz : Estimation of the Chooz cores fission rates and associated errors in the framework of the Double Chooz experiment.” 2014. Web. 25 Sep 2020.

Vancouver:

Onillon A. Prédiction des taux de fission des coeurs de Chooz et estimation des incertitudes associées dans le cadre de l'expérience Double Chooz : Estimation of the Chooz cores fission rates and associated errors in the framework of the Double Chooz experiment. [Internet] [Doctoral dissertation]. Nantes, Ecole des Mines; 2014. [cited 2020 Sep 25]. Available from: http://www.theses.fr/2014EMNA0116.

Council of Science Editors:

Onillon A. Prédiction des taux de fission des coeurs de Chooz et estimation des incertitudes associées dans le cadre de l'expérience Double Chooz : Estimation of the Chooz cores fission rates and associated errors in the framework of the Double Chooz experiment. [Doctoral Dissertation]. Nantes, Ecole des Mines; 2014. Available from: http://www.theses.fr/2014EMNA0116


Brno University of Technology

26. Filová, Vendula. Optimalizace neutronového spektra podkritického jaderného reaktoru se spalačním zdrojem: Neutron spectra optimisation of subcritical nuclear reactor with spallation neutron source.

Degree: 2019, Brno University of Technology

 The bachelor thesis deals with accelerator-driven systems and principles of their functioning. The theoretical part indcludes a description of system components and it also introduces… (more)

Subjects/Keywords: ADS; ADTT; BURAN; MCNP; spalační reakce; terč; urychlovačem řízený systém; ADS; ADTT; BURAN; MCNP; spallation reaction; target; accelerator-driven system

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Filová, V. (2019). Optimalizace neutronového spektra podkritického jaderného reaktoru se spalačním zdrojem: Neutron spectra optimisation of subcritical nuclear reactor with spallation neutron source. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/173692

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):

Filová, Vendula. “Optimalizace neutronového spektra podkritického jaderného reaktoru se spalačním zdrojem: Neutron spectra optimisation of subcritical nuclear reactor with spallation neutron source.” 2019. Thesis, Brno University of Technology. Accessed September 25, 2020. http://hdl.handle.net/11012/173692.

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

MLA Handbook (7th Edition):

Filová, Vendula. “Optimalizace neutronového spektra podkritického jaderného reaktoru se spalačním zdrojem: Neutron spectra optimisation of subcritical nuclear reactor with spallation neutron source.” 2019. Web. 25 Sep 2020.

Vancouver:

Filová V. Optimalizace neutronového spektra podkritického jaderného reaktoru se spalačním zdrojem: Neutron spectra optimisation of subcritical nuclear reactor with spallation neutron source. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/11012/173692.

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

Council of Science Editors:

Filová V. Optimalizace neutronového spektra podkritického jaderného reaktoru se spalačním zdrojem: Neutron spectra optimisation of subcritical nuclear reactor with spallation neutron source. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/173692

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

27. Somaini, Alice. Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules : Analysis of Biases Induced by a Simplified Modelisation on PWR Fuel Evolution-Neutron Leakage Impact in the Cell Calculations.

Degree: Docteur es, Énergie nucléaire, 2017, Université Paris-Saclay (ComUE)

Les études de scénarios d'un parc électronucléaire, ainsi que les études de sûreté, sont essentielles pour explorer les différentes stratégies du nucléaire du futur. Pour… (more)

Subjects/Keywords: Simulations réacteurs nucléaires; Fuites neutroniques; MCNP évoluant; Incertitudes; Calcul cellule; Nuclear reactor simulations; Neutron leakage; MCNP depletion calculation; Biases; Cell calcualtion

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Somaini, A. (2017). Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules : Analysis of Biases Induced by a Simplified Modelisation on PWR Fuel Evolution-Neutron Leakage Impact in the Cell Calculations. (Doctoral Dissertation). Université Paris-Saclay (ComUE). Retrieved from http://www.theses.fr/2017SACLS271

Chicago Manual of Style (16th Edition):

Somaini, Alice. “Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules : Analysis of Biases Induced by a Simplified Modelisation on PWR Fuel Evolution-Neutron Leakage Impact in the Cell Calculations.” 2017. Doctoral Dissertation, Université Paris-Saclay (ComUE). Accessed September 25, 2020. http://www.theses.fr/2017SACLS271.

MLA Handbook (7th Edition):

Somaini, Alice. “Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules : Analysis of Biases Induced by a Simplified Modelisation on PWR Fuel Evolution-Neutron Leakage Impact in the Cell Calculations.” 2017. Web. 25 Sep 2020.

Vancouver:

Somaini A. Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules : Analysis of Biases Induced by a Simplified Modelisation on PWR Fuel Evolution-Neutron Leakage Impact in the Cell Calculations. [Internet] [Doctoral dissertation]. Université Paris-Saclay (ComUE); 2017. [cited 2020 Sep 25]. Available from: http://www.theses.fr/2017SACLS271.

Council of Science Editors:

Somaini A. Analyse des erreurs induites par une modélisation simplifiée sur l’évolution des combustibles REP Impact des fuites neutroniques dans les calculs cellules : Analysis of Biases Induced by a Simplified Modelisation on PWR Fuel Evolution-Neutron Leakage Impact in the Cell Calculations. [Doctoral Dissertation]. Université Paris-Saclay (ComUE); 2017. Available from: http://www.theses.fr/2017SACLS271


Brno University of Technology

28. Konček, Róbert. Simulace stínění ionizujícího záření programem MCNP: Ionizing radiation shielding simulation using MCNP code.

Degree: 2019, Brno University of Technology

 Radiation is defined as ionizing if it has enough energy to remove electrons from atoms or molecules when it passes through or collides with matter.… (more)

Subjects/Keywords: Gama spektroskopia; tienenie ionizujúceho žiarenia; MCNP; Monte Carlo.; Gamma spectroscopy; ionizing radiation shielding; MCNP; Monte Carlo.

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Konček, R. (2019). Simulace stínění ionizujícího záření programem MCNP: Ionizing radiation shielding simulation using MCNP code. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/39477

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):

Konček, Róbert. “Simulace stínění ionizujícího záření programem MCNP: Ionizing radiation shielding simulation using MCNP code.” 2019. Thesis, Brno University of Technology. Accessed September 25, 2020. http://hdl.handle.net/11012/39477.

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

MLA Handbook (7th Edition):

Konček, Róbert. “Simulace stínění ionizujícího záření programem MCNP: Ionizing radiation shielding simulation using MCNP code.” 2019. Web. 25 Sep 2020.

Vancouver:

Konček R. Simulace stínění ionizujícího záření programem MCNP: Ionizing radiation shielding simulation using MCNP code. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/11012/39477.

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

Council of Science Editors:

Konček R. Simulace stínění ionizujícího záření programem MCNP: Ionizing radiation shielding simulation using MCNP code. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/39477

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


Texas A&M University

29. Marcantel, Grace Ann. Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies.

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

 The Fluoride High-Temperature Reactor (FHR) and the Very High-Temperature Reactor (VHTR) are advanced reactor designs in the generation IV class. Advanced reactors operate in more… (more)

Subjects/Keywords: TRIGA; FHR; VHTR; energy spectrum; MCNP; similarity factors

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Marcantel, G. A. (2018). Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/173485

Chicago Manual of Style (16th Edition):

Marcantel, Grace Ann. “Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies.” 2018. Masters Thesis, Texas A&M University. Accessed September 25, 2020. http://hdl.handle.net/1969.1/173485.

MLA Handbook (7th Edition):

Marcantel, Grace Ann. “Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies.” 2018. Web. 25 Sep 2020.

Vancouver:

Marcantel GA. Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies. [Internet] [Masters thesis]. Texas A&M University; 2018. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/1969.1/173485.

Council of Science Editors:

Marcantel GA. Analysis of Neutron Environments in Advanced Reactors Vs. Triga Reactor for In-Core Behavior Studies. [Masters Thesis]. Texas A&M University; 2018. Available from: http://hdl.handle.net/1969.1/173485


Texas A&M University

30. Redd, Randall Alex. Radiation dosimetry and medical physics calculations using MCNP 5.

Degree: MS, Health Physics, 2004, Texas A&M University

 Six radiation dosimetry and medical physics problems were analyzed using a beta version of MCNP 5 as part of an international intercomparison of radiation dosimetry… (more)

Subjects/Keywords: Radiation Dosimetry; Medical Physics; MCNP

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Redd, R. A. (2004). Radiation dosimetry and medical physics calculations using MCNP 5. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/467

Chicago Manual of Style (16th Edition):

Redd, Randall Alex. “Radiation dosimetry and medical physics calculations using MCNP 5.” 2004. Masters Thesis, Texas A&M University. Accessed September 25, 2020. http://hdl.handle.net/1969.1/467.

MLA Handbook (7th Edition):

Redd, Randall Alex. “Radiation dosimetry and medical physics calculations using MCNP 5.” 2004. Web. 25 Sep 2020.

Vancouver:

Redd RA. Radiation dosimetry and medical physics calculations using MCNP 5. [Internet] [Masters thesis]. Texas A&M University; 2004. [cited 2020 Sep 25]. Available from: http://hdl.handle.net/1969.1/467.

Council of Science Editors:

Redd RA. Radiation dosimetry and medical physics calculations using MCNP 5. [Masters Thesis]. Texas A&M University; 2004. Available from: http://hdl.handle.net/1969.1/467

[1] [2] [3] [4] [5]

.