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You searched for subject:(MCNP). Showing records 1 – 30 of 135 total matches.

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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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Dalborg E. MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2. [Internet] [Thesis]. Uppsala University; 2013. [cited 2019 Mar 23]. 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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Benson BC. Feasibility of creating a neutron detector array for the detection of special nuclear materials. [Internet] [Masters thesis]. Georgia Tech; 2015. [cited 2019 Mar 23]. 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


Texas A&M University

4. Hiatt, Matthew Torgerson. TXSAMC (transport cross sections from applied Monte Carlo): a new tool for generating shielded multigroup cross sections.

Degree: 2009, Texas A&M University

 This thesis describes a tool called TXSAMC (Transport Cross Sections from Applied Monte Carlo) that produces shielded and homogenized multigroup cross sections for small fast… (more)

Subjects/Keywords: MCNP; cross sections; TRANSX

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APA (6th Edition):

Hiatt, M. T. (2009). TXSAMC (transport cross sections from applied Monte Carlo): a new tool for generating shielded multigroup cross sections. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1945

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):

Hiatt, Matthew Torgerson. “TXSAMC (transport cross sections from applied Monte Carlo): a new tool for generating shielded multigroup cross sections.” 2009. Thesis, Texas A&M University. Accessed March 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1945.

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

MLA Handbook (7th Edition):

Hiatt, Matthew Torgerson. “TXSAMC (transport cross sections from applied Monte Carlo): a new tool for generating shielded multigroup cross sections.” 2009. Web. 23 Mar 2019.

Vancouver:

Hiatt MT. TXSAMC (transport cross sections from applied Monte Carlo): a new tool for generating shielded multigroup cross sections. [Internet] [Thesis]. Texas A&M University; 2009. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1945.

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

Council of Science Editors:

Hiatt MT. TXSAMC (transport cross sections from applied Monte Carlo): a new tool for generating shielded multigroup cross sections. [Thesis]. Texas A&M University; 2009. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1945

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


University of Toledo

5. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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


McMaster University

6. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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 Tennessee – Knoxville

7. Grogan, Brandon Robert. The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging.

Degree: 2010, University of Tennessee – Knoxville

 This dissertation presents a novel method for removing scattering effects from Nuclear Materials Identification System (NMIS) imaging. The NMIS uses fast neutron radiography to generate… (more)

Subjects/Keywords: neutron radiography; scatter removal; MCNP modeling; MCNP-PoliMi; NMIS; Nuclear Engineering

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APA (6th Edition):

Grogan, B. R. (2010). The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/692

Chicago Manual of Style (16th Edition):

Grogan, Brandon Robert. “The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging.” 2010. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed March 23, 2019. https://trace.tennessee.edu/utk_graddiss/692.

MLA Handbook (7th Edition):

Grogan, Brandon Robert. “The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging.” 2010. Web. 23 Mar 2019.

Vancouver:

Grogan BR. The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2010. [cited 2019 Mar 23]. Available from: https://trace.tennessee.edu/utk_graddiss/692.

Council of Science Editors:

Grogan BR. The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2010. Available from: https://trace.tennessee.edu/utk_graddiss/692


University of Ontario Institute of Technology

8. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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 Ontario Institute of Technology

9. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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

10. 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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Gilbert J. Simulation of in-core dose rates for an offline CANDU reactor. [Internet] [Thesis]. University of Ontario Institute of Technology; 2016. [cited 2019 Mar 23]. 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


Texas A&M University

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

Degree: 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

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APA (6th Edition):

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

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):

Holzaepfel, Aaron J. “High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite.” 2016. Thesis, Texas A&M University. Accessed March 23, 2019. http://hdl.handle.net/1969.1/157938.

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

MLA Handbook (7th Edition):

Holzaepfel, Aaron J. “High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite.” 2016. Web. 23 Mar 2019.

Vancouver:

Holzaepfel AJ. High Fidelity Deterministic Solution of Neutron Transport Problems in Graphite. [Internet] [Thesis]. Texas A&M University; 2016. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/1969.1/157938.

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

Council of Science Editors:

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

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


Texas A&M University

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

Degree: 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

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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. (Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517

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):

Joe Justina, -. “Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal.” 2012. Thesis, Texas A&M University. Accessed March 23, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517.

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

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. 23 Mar 2019.

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] [Thesis]. Texas A&M University; 2012. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517.

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

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. [Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2012-08-11517

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

13. 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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Henrique Ribeiro Peixoto P. Desenvolvimento de um modelo computacional para avaliações dosimétricas em ratos . [Internet] [Thesis]. Universidade Federal de Pernambuco; 2008. [cited 2019 Mar 23]. 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


Virginia Commonwealth University

14. Britt, Taylor C. Innovative Fuel Design to Improve Proliferation Management.

Degree: MS, Mechanical and Nuclear Engineering, 2018, Virginia Commonwealth University

  This research uses an existing innovative fuel design (IFD) that has intrinsic safety features and enhanced economics over the current uranium dioxide (UO2) light… (more)

Subjects/Keywords: Nuclear; Nonproliferation; Fuel; Plutonium; MCNP; Nuclear Engineering

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APA (6th Edition):

Britt, T. C. (2018). Innovative Fuel Design to Improve Proliferation Management. (Thesis). Virginia Commonwealth University. Retrieved from https://scholarscompass.vcu.edu/etd/5690

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):

Britt, Taylor C. “Innovative Fuel Design to Improve Proliferation Management.” 2018. Thesis, Virginia Commonwealth University. Accessed March 23, 2019. https://scholarscompass.vcu.edu/etd/5690.

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

MLA Handbook (7th Edition):

Britt, Taylor C. “Innovative Fuel Design to Improve Proliferation Management.” 2018. Web. 23 Mar 2019.

Vancouver:

Britt TC. Innovative Fuel Design to Improve Proliferation Management. [Internet] [Thesis]. Virginia Commonwealth University; 2018. [cited 2019 Mar 23]. Available from: https://scholarscompass.vcu.edu/etd/5690.

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

Council of Science Editors:

Britt TC. Innovative Fuel Design to Improve Proliferation Management. [Thesis]. Virginia Commonwealth University; 2018. Available from: https://scholarscompass.vcu.edu/etd/5690

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


Université Catholique de Louvain

15. Massinon, Lucien. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core.

Degree: 2017, Université Catholique de Louvain

ALEPH is a Monte-Carlo burn-up code which is being developed in SCK-CEN (Studie Centrum voor de Kern energie - Centre d’Etude de l’énergie Nucléaire, Belgium)… (more)

Subjects/Keywords: ALEPH2; MCNP; nuclear science; depletion code

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APA (6th Edition):

Massinon, L. (2017). Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core. (Thesis). Université Catholique de Louvain. Retrieved from http://hdl.handle.net/2078.1/thesis:13049

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):

Massinon, Lucien. “Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core.” 2017. Thesis, Université Catholique de Louvain. Accessed March 23, 2019. http://hdl.handle.net/2078.1/thesis:13049.

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

MLA Handbook (7th Edition):

Massinon, Lucien. “Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core.” 2017. Web. 23 Mar 2019.

Vancouver:

Massinon L. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core. [Internet] [Thesis]. Université Catholique de Louvain; 2017. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/2078.1/thesis:13049.

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

Council of Science Editors:

Massinon L. Validation of ALEPH2 depletion code on the spent fuel isotopic content of samples irradiated in Gösgen PWR core. [Thesis]. Université Catholique de Louvain; 2017. Available from: http://hdl.handle.net/2078.1/thesis:13049

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


Uppsala University

16. Fridström, Richard. Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor.

Degree: Applied Nuclear Physics, 2010, Uppsala University

  In order to monitor a nuclear boiling water reactor fixed and movable detectors are used, such as the neutron sensitive LPRM (Local Power Range… (more)

Subjects/Keywords: TIP; BWR; gamma; detector; MCNP; POLCA

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APA (6th Edition):

Fridström, R. (2010). Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969

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):

Fridström, Richard. “Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor.” 2010. Thesis, Uppsala University. Accessed March 23, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969.

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

MLA Handbook (7th Edition):

Fridström, Richard. “Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor.” 2010. Web. 23 Mar 2019.

Vancouver:

Fridström R. Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor. [Internet] [Thesis]. Uppsala University; 2010. [cited 2019 Mar 23]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969.

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

Council of Science Editors:

Fridström R. Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor. [Thesis]. Uppsala University; 2010. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-126969

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


University of Tennessee – Knoxville

17. 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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Wilkerson RB. A Bayesian Approach to Aerial Localization of Radioactive Sources. [Internet] [Thesis]. University of Tennessee – Knoxville; 2016. [cited 2019 Mar 23]. 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


Texas A&M University

18. 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

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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/1969.1/173727

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 March 23, 2019. http://hdl.handle.net/1969.1/173727.

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. 23 Mar 2019.

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 2019 Mar 23]. Available from: http://hdl.handle.net/1969.1/173727.

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/1969.1/173727


Texas A&M University

19. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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


University of Texas – Austin

20. Wang, Siqiu. Modeling of NORM dosimetry in onshore oilfields using Monte Carlo methods.

Degree: Mechanical Engineering, 2016, University of Texas – Austin

 NORM wastes generated in the oil and gas industry create a radioactive environment for the workers in the field. Modeling and understanding the radiation doses… (more)

Subjects/Keywords: MCNP; Dosimetry; NORM; Oil and gas industry

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APA (6th Edition):

Wang, S. (2016). Modeling of NORM dosimetry in onshore oilfields using Monte Carlo methods. (Thesis). University of Texas – Austin. Retrieved from http://hdl.handle.net/2152/44601

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):

Wang, Siqiu. “Modeling of NORM dosimetry in onshore oilfields using Monte Carlo methods.” 2016. Thesis, University of Texas – Austin. Accessed March 23, 2019. http://hdl.handle.net/2152/44601.

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

MLA Handbook (7th Edition):

Wang, Siqiu. “Modeling of NORM dosimetry in onshore oilfields using Monte Carlo methods.” 2016. Web. 23 Mar 2019.

Vancouver:

Wang S. Modeling of NORM dosimetry in onshore oilfields using Monte Carlo methods. [Internet] [Thesis]. University of Texas – Austin; 2016. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/2152/44601.

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

Council of Science Editors:

Wang S. Modeling of NORM dosimetry in onshore oilfields using Monte Carlo methods. [Thesis]. University of Texas – Austin; 2016. Available from: http://hdl.handle.net/2152/44601

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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Antunes PCG. Reconstrução de objetos simuladores segmentados aplicáveis à dosimetria de pele. [Internet] [Masters thesis]. University of São Paulo; 2010. [cited 2019 Mar 23]. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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

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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 March 23, 2019. 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. 23 Mar 2019.

Vancouver:

Tada A. Análise dosimétrica de fontes de radiação para uso de lesões dermatológicas. [Internet] [Masters thesis]. University of São Paulo; 2010. [cited 2019 Mar 23]. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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. 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, Paris Saclay

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

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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). Paris Saclay. 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, Paris Saclay. Accessed March 23, 2019. 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. 23 Mar 2019.

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]. Paris Saclay; 2017. [cited 2019 Mar 23]. 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]. Paris Saclay; 2017. Available from: http://www.theses.fr/2017SACLS271

26. 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

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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 March 23, 2019. 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. 23 Mar 2019.

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 2019 Mar 23]. 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

27. Konček, Róbert. Simulace stínění ionizujícího záření programem MCNP .

Degree: 2015, Brno University of Technology

 Žiarenie je definované ako ionizujúce, ak má dostatok energie na vytrhnutie elektrónov z atómov alebo molekúl, počas jeho prechodu látkovým prostredím. Z tejto schopnosti vyplýva… (more)

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

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

APA (6th Edition):

Konček, R. (2015). Simulace stínění ionizujícího záření programem MCNP . (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 .” 2015. Thesis, Brno University of Technology. Accessed March 23, 2019. 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 .” 2015. Web. 23 Mar 2019.

Vancouver:

Konček R. Simulace stínění ionizujícího záření programem MCNP . [Internet] [Thesis]. Brno University of Technology; 2015. [cited 2019 Mar 23]. 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 . [Thesis]. Brno University of Technology; 2015. 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

28. Niclas, Halldin. MCNP5 Criticality Safety Modeling and Validation for LWR Fuel Cycle Applications.

Degree: 2013, Chalmers University of Technology

 This thesis considers criticality safety in the production and storage stages of the light water reactor fuel cycle using the Monte Carlo N-Particle (MCNP) neutron… (more)

Subjects/Keywords: MCNP; MCNP5; PWR; criticality safety; LWR; validation; criticality

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

APA (6th Edition):

Niclas, H. (2013). MCNP5 Criticality Safety Modeling and Validation for LWR Fuel Cycle Applications. (Thesis). Chalmers University of Technology. Retrieved from http://studentarbeten.chalmers.se/publication/180157-mcnp5-criticality-safety-modeling-and-validation-for-lwr-fuel-cycle-applications

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):

Niclas, Halldin. “MCNP5 Criticality Safety Modeling and Validation for LWR Fuel Cycle Applications.” 2013. Thesis, Chalmers University of Technology. Accessed March 23, 2019. http://studentarbeten.chalmers.se/publication/180157-mcnp5-criticality-safety-modeling-and-validation-for-lwr-fuel-cycle-applications.

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

MLA Handbook (7th Edition):

Niclas, Halldin. “MCNP5 Criticality Safety Modeling and Validation for LWR Fuel Cycle Applications.” 2013. Web. 23 Mar 2019.

Vancouver:

Niclas H. MCNP5 Criticality Safety Modeling and Validation for LWR Fuel Cycle Applications. [Internet] [Thesis]. Chalmers University of Technology; 2013. [cited 2019 Mar 23]. Available from: http://studentarbeten.chalmers.se/publication/180157-mcnp5-criticality-safety-modeling-and-validation-for-lwr-fuel-cycle-applications.

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

Council of Science Editors:

Niclas H. MCNP5 Criticality Safety Modeling and Validation for LWR Fuel Cycle Applications. [Thesis]. Chalmers University of Technology; 2013. Available from: http://studentarbeten.chalmers.se/publication/180157-mcnp5-criticality-safety-modeling-and-validation-for-lwr-fuel-cycle-applications

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

29. Kumar, Ashita. An experimental study of the relative response of plastic scintillators to photons and beta particles within the context of tritium monitoring.

Degree: 2011, University of Ontario Institute of Technology

 A scintillation counting system has been constructed with the use of BC-400 and EJ-212 series plastic scintillators along with a subminiature photomultiplier tube to investigate… (more)

Subjects/Keywords: Plastic scintillator; Tritium; MCNP; Gamma photons; Beta particles

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

APA (6th Edition):

Kumar, A. (2011). An experimental study of the relative response of plastic scintillators to photons and beta particles within the context of tritium monitoring. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/177

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):

Kumar, Ashita. “An experimental study of the relative response of plastic scintillators to photons and beta particles within the context of tritium monitoring.” 2011. Thesis, University of Ontario Institute of Technology. Accessed March 23, 2019. http://hdl.handle.net/10155/177.

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

MLA Handbook (7th Edition):

Kumar, Ashita. “An experimental study of the relative response of plastic scintillators to photons and beta particles within the context of tritium monitoring.” 2011. Web. 23 Mar 2019.

Vancouver:

Kumar A. An experimental study of the relative response of plastic scintillators to photons and beta particles within the context of tritium monitoring. [Internet] [Thesis]. University of Ontario Institute of Technology; 2011. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/10155/177.

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

Council of Science Editors:

Kumar A. An experimental study of the relative response of plastic scintillators to photons and beta particles within the context of tritium monitoring. [Thesis]. University of Ontario Institute of Technology; 2011. Available from: http://hdl.handle.net/10155/177

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

30. Malabre-O'Sullivan, Neville. Low energy photon mimic of the tritium beta decay energy spectrum.

Degree: 2013, University of Ontario Institute of Technology

 Tritium is a radioactive hydrogen isotope that is typically produced via neutron interaction with heavy water (D2O), producing tritiated water (DTO). As a result of… (more)

Subjects/Keywords: Tritium; MCNP; Low energy electrons; Biophysics; Characteristic x-rays

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

APA (6th Edition):

Malabre-O'Sullivan, N. (2013). Low energy photon mimic of the tritium beta decay energy spectrum. (Thesis). University of Ontario Institute of Technology. Retrieved from http://hdl.handle.net/10155/306

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):

Malabre-O'Sullivan, Neville. “Low energy photon mimic of the tritium beta decay energy spectrum.” 2013. Thesis, University of Ontario Institute of Technology. Accessed March 23, 2019. http://hdl.handle.net/10155/306.

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

MLA Handbook (7th Edition):

Malabre-O'Sullivan, Neville. “Low energy photon mimic of the tritium beta decay energy spectrum.” 2013. Web. 23 Mar 2019.

Vancouver:

Malabre-O'Sullivan N. Low energy photon mimic of the tritium beta decay energy spectrum. [Internet] [Thesis]. University of Ontario Institute of Technology; 2013. [cited 2019 Mar 23]. Available from: http://hdl.handle.net/10155/306.

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

Council of Science Editors:

Malabre-O'Sullivan N. Low energy photon mimic of the tritium beta decay energy spectrum. [Thesis]. University of Ontario Institute of Technology; 2013. Available from: http://hdl.handle.net/10155/306

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

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