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You searched for subject:(Reator Nuclear Combust vel Nuclear Analises qu mica). Showing records 1 – 30 of 4945 total matches.

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1. Kelly Cristina Martins Faêda. Caracterização do combustível para reatores nucleares produtores de hidrogênio.

Degree: Master, 2011, Centro de Desenvolvimento da Tecnologia Nuclear

Reatores nucleares de 4 geração do tipo HTGR (reatores de alta temperatura refrigerados a gás) apresentam vantagens em relação a um reator a água pressurizada,… (more)

Subjects/Keywords: COMBUSTIVEL NUCLEAR; Reator Nuclear Combustível Nuclear Analises química; Nuclear fuel Nuclear reactor Chemical analysis

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APA (6th Edition):

Faêda, K. C. M. (2011). Caracterização do combustível para reatores nucleares produtores de hidrogênio. (Masters Thesis). Centro de Desenvolvimento da Tecnologia Nuclear. Retrieved from http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;

Chicago Manual of Style (16th Edition):

Faêda, Kelly Cristina Martins. “Caracterização do combustível para reatores nucleares produtores de hidrogênio.” 2011. Masters Thesis, Centro de Desenvolvimento da Tecnologia Nuclear. Accessed June 20, 2019. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;.

MLA Handbook (7th Edition):

Faêda, Kelly Cristina Martins. “Caracterização do combustível para reatores nucleares produtores de hidrogênio.” 2011. Web. 20 Jun 2019.

Vancouver:

Faêda KCM. Caracterização do combustível para reatores nucleares produtores de hidrogênio. [Internet] [Masters thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2011. [cited 2019 Jun 20]. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;.

Council of Science Editors:

Faêda KCM. Caracterização do combustível para reatores nucleares produtores de hidrogênio. [Masters Thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2011. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=139 ;

2. Tondin, Julio Benedito Marin. Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear.

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

Em instalações nucleares o controle do material nuclear é uma das atividades da maior importância. A Comissão Nacional de Energia Nuclear (CNEN) e a Agencia… (more)

Subjects/Keywords: material nuclear; nuclear material; nuclear reactor; reator nuclear; safeguard; salvaguarda

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APA (6th Edition):

Tondin, J. B. M. (2011). Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85131/tde-03042012-110437/ ;

Chicago Manual of Style (16th Edition):

Tondin, Julio Benedito Marin. “Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear.” 2011. Masters Thesis, University of São Paulo. Accessed June 20, 2019. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-03042012-110437/ ;.

MLA Handbook (7th Edition):

Tondin, Julio Benedito Marin. “Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear.” 2011. Web. 20 Jun 2019.

Vancouver:

Tondin JBM. Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear. [Internet] [Masters thesis]. University of São Paulo; 2011. [cited 2019 Jun 20]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85131/tde-03042012-110437/ ;.

Council of Science Editors:

Tondin JBM. Desenvolvimento de um programa computacional para gerenciamento de banco de dados de material nuclear. [Masters Thesis]. University of São Paulo; 2011. Available from: http://www.teses.usp.br/teses/disponiveis/85/85131/tde-03042012-110437/ ;

3. Yancey, Kristina. Nationwide Used Fuel Inventory Analysis.

Degree: 2013, Texas Digital Library

 The goal of this research was to develop a methodology to collect inventory estimates for the analysis and characterization of used fuel in the United… (more)

Subjects/Keywords: nuclear

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APA (6th Edition):

Yancey, K. (2013). Nationwide Used Fuel Inventory Analysis. (Thesis). Texas Digital Library. Retrieved from http://hdl.handle.net/1969; http://hdl.handle.net/2249.1/66759

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):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Thesis, Texas Digital Library. Accessed June 20, 2019. http://hdl.handle.net/1969; http://hdl.handle.net/2249.1/66759.

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

MLA Handbook (7th Edition):

Yancey, Kristina. “Nationwide Used Fuel Inventory Analysis.” 2013. Web. 20 Jun 2019.

Vancouver:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Internet] [Thesis]. Texas Digital Library; 2013. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969; http://hdl.handle.net/2249.1/66759.

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

Council of Science Editors:

Yancey K. Nationwide Used Fuel Inventory Analysis. [Thesis]. Texas Digital Library; 2013. Available from: http://hdl.handle.net/1969; http://hdl.handle.net/2249.1/66759

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


University of Tennessee – Knoxville

4. Schmitt, Kyle Thomas. Population of low-lying levels in the one-neutron halo nucleus 11Be via the neutron transfer reaction 10Be(d,p).

Degree: 2011, University of Tennessee – Knoxville

 Historically, measurements of differential cross-sections for the neutron transfer reaction (d, p) on stable targets have been an important tool for extracting spectroscopic information. In… (more)

Subjects/Keywords: Nuclear

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APA (6th Edition):

Schmitt, K. T. (2011). Population of low-lying levels in the one-neutron halo nucleus 11Be via the neutron transfer reaction 10Be(d,p). (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/1223

Chicago Manual of Style (16th Edition):

Schmitt, Kyle Thomas. “Population of low-lying levels in the one-neutron halo nucleus 11Be via the neutron transfer reaction 10Be(d,p).” 2011. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed June 20, 2019. https://trace.tennessee.edu/utk_graddiss/1223.

MLA Handbook (7th Edition):

Schmitt, Kyle Thomas. “Population of low-lying levels in the one-neutron halo nucleus 11Be via the neutron transfer reaction 10Be(d,p).” 2011. Web. 20 Jun 2019.

Vancouver:

Schmitt KT. Population of low-lying levels in the one-neutron halo nucleus 11Be via the neutron transfer reaction 10Be(d,p). [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2011. [cited 2019 Jun 20]. Available from: https://trace.tennessee.edu/utk_graddiss/1223.

Council of Science Editors:

Schmitt KT. Population of low-lying levels in the one-neutron halo nucleus 11Be via the neutron transfer reaction 10Be(d,p). [Doctoral Dissertation]. University of Tennessee – Knoxville; 2011. Available from: https://trace.tennessee.edu/utk_graddiss/1223


Wayne State University

5. Lapointe, Sarah. D meson reconstruction at star using the silicon vertex tracker (svt).

Degree: PhD, Physics and Astronomy, 2010, Wayne State University

  At the Relativistic Heavy Ion Collider a hot and dense matter is produced in Au+Au collisions at sqrt(sNN) = 200 GeV/c. This matter exhibits… (more)

Subjects/Keywords: Nuclear

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APA (6th Edition):

Lapointe, S. (2010). D meson reconstruction at star using the silicon vertex tracker (svt). (Doctoral Dissertation). Wayne State University. Retrieved from https://digitalcommons.wayne.edu/oa_dissertations/247

Chicago Manual of Style (16th Edition):

Lapointe, Sarah. “D meson reconstruction at star using the silicon vertex tracker (svt).” 2010. Doctoral Dissertation, Wayne State University. Accessed June 20, 2019. https://digitalcommons.wayne.edu/oa_dissertations/247.

MLA Handbook (7th Edition):

Lapointe, Sarah. “D meson reconstruction at star using the silicon vertex tracker (svt).” 2010. Web. 20 Jun 2019.

Vancouver:

Lapointe S. D meson reconstruction at star using the silicon vertex tracker (svt). [Internet] [Doctoral dissertation]. Wayne State University; 2010. [cited 2019 Jun 20]. Available from: https://digitalcommons.wayne.edu/oa_dissertations/247.

Council of Science Editors:

Lapointe S. D meson reconstruction at star using the silicon vertex tracker (svt). [Doctoral Dissertation]. Wayne State University; 2010. Available from: https://digitalcommons.wayne.edu/oa_dissertations/247


Universidade do Rio Grande do Sul

6. Ceolin, Celina. A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo : avaliação do fluxo para problemas estacionários e de cinética.

Degree: 2014, Universidade do Rio Grande do Sul

Na presente tese é resolvida a equação de difusão de nêutrons estacionária, bem como problemas de cinética, em geometria unidimensional cartesiana multi-região considerando o modelo… (more)

Subjects/Keywords: Equações de transporte de neutrons; Structural optimization; Meta-heuristic algorithms; Reator nuclear; Métodos numéricos; Harmony search; Firefly algorithm; Truss structures

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APA (6th Edition):

Ceolin, C. (2014). A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo : avaliação do fluxo para problemas estacionários e de cinética. (Thesis). Universidade do Rio Grande do Sul. Retrieved from http://hdl.handle.net/10183/96762

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):

Ceolin, Celina. “A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo : avaliação do fluxo para problemas estacionários e de cinética.” 2014. Thesis, Universidade do Rio Grande do Sul. Accessed June 20, 2019. http://hdl.handle.net/10183/96762.

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

MLA Handbook (7th Edition):

Ceolin, Celina. “A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo : avaliação do fluxo para problemas estacionários e de cinética.” 2014. Web. 20 Jun 2019.

Vancouver:

Ceolin C. A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo : avaliação do fluxo para problemas estacionários e de cinética. [Internet] [Thesis]. Universidade do Rio Grande do Sul; 2014. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/10183/96762.

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

Council of Science Editors:

Ceolin C. A equação unidimensional de difusão de nêutrons com modelo multigrupo de energia e meio heterogêneo : avaliação do fluxo para problemas estacionários e de cinética. [Thesis]. Universidade do Rio Grande do Sul; 2014. Available from: http://hdl.handle.net/10183/96762

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


Iowa State University

7. Perry, Joshua Paul. A novel approach to central-jet forward-hadron correlations in proton-proton collisions at 200 GeV at the PHENIX experiment.

Degree: 2014, Iowa State University

 The results of Semi-Inclusive Deep Inelastic Scattering and Deep Inelastic Scattering experiments combined in a global analysis have shown us that a transversely polarized quark… (more)

Subjects/Keywords: Nuclear Physics; Nuclear; Spin; Nuclear

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APA (6th Edition):

Perry, J. P. (2014). A novel approach to central-jet forward-hadron correlations in proton-proton collisions at 200 GeV at the PHENIX experiment. (Thesis). Iowa State University. Retrieved from https://lib.dr.iastate.edu/etd/14209

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):

Perry, Joshua Paul. “A novel approach to central-jet forward-hadron correlations in proton-proton collisions at 200 GeV at the PHENIX experiment.” 2014. Thesis, Iowa State University. Accessed June 20, 2019. https://lib.dr.iastate.edu/etd/14209.

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

MLA Handbook (7th Edition):

Perry, Joshua Paul. “A novel approach to central-jet forward-hadron correlations in proton-proton collisions at 200 GeV at the PHENIX experiment.” 2014. Web. 20 Jun 2019.

Vancouver:

Perry JP. A novel approach to central-jet forward-hadron correlations in proton-proton collisions at 200 GeV at the PHENIX experiment. [Internet] [Thesis]. Iowa State University; 2014. [cited 2019 Jun 20]. Available from: https://lib.dr.iastate.edu/etd/14209.

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

Council of Science Editors:

Perry JP. A novel approach to central-jet forward-hadron correlations in proton-proton collisions at 200 GeV at the PHENIX experiment. [Thesis]. Iowa State University; 2014. Available from: https://lib.dr.iastate.edu/etd/14209

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

8. Arêdes, Vitor Ottoni Garcia. Caracterização do núcleo cilíndrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuição espacial e energética do fluxo de nêutrons.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2014, University of São Paulo

Neste trabalho foi realizado o mapeamento do fluxo de nêutrons térmicos e epitérmicos e o espectro energético dos nêutrons no núcleo do Reator IPEN/MB-01, em… (more)

Subjects/Keywords: activation foils; análise por ativação; cylindrical core; espectro de nêutrons; fluxo de nêutrons; neutron flux; nuclear reactor; núcleo cilíndrico; reator nuclear; spectrum of neutrons

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APA (6th Edition):

Arêdes, V. O. G. (2014). Caracterização do núcleo cilíndrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuição espacial e energética do fluxo de nêutrons. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02122014-133231/ ;

Chicago Manual of Style (16th Edition):

Arêdes, Vitor Ottoni Garcia. “Caracterização do núcleo cilíndrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuição espacial e energética do fluxo de nêutrons.” 2014. Masters Thesis, University of São Paulo. Accessed June 20, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02122014-133231/ ;.

MLA Handbook (7th Edition):

Arêdes, Vitor Ottoni Garcia. “Caracterização do núcleo cilíndrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuição espacial e energética do fluxo de nêutrons.” 2014. Web. 20 Jun 2019.

Vancouver:

Arêdes VOG. Caracterização do núcleo cilíndrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuição espacial e energética do fluxo de nêutrons. [Internet] [Masters thesis]. University of São Paulo; 2014. [cited 2019 Jun 20]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02122014-133231/ ;.

Council of Science Editors:

Arêdes VOG. Caracterização do núcleo cilíndrico de menor excesso de reatividade do reator IPEN/MB-01, pela medida da distribuição espacial e energética do fluxo de nêutrons. [Masters Thesis]. University of São Paulo; 2014. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-02122014-133231/ ;

9. Taddei, Maria Helena Tirollo. Determinação de fatores de escala para estimativa do inventário de radionuclídeos em rejeitos de média e baixa atividades do reator IEA-R1.

Degree: PhD, Tecnologia Nuclear - Reatores, 2013, University of São Paulo

Em cumprimento às normas que regulam a transferência e deposição final de rejeitos radioativos, o inventário de radionuclídeos de cada embalado contendo tais rejeitos deve… (more)

Subjects/Keywords: difficult to measure radionuclides; fatores de escala; radioactive wastes; radiochemistry; radionuclídeos de difícil medição; radioquímica; reator nuclear de pesquisa; rejeitos radioativos; research nuclear reactor; scaling fator

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APA (6th Edition):

Taddei, M. H. T. (2013). Determinação de fatores de escala para estimativa do inventário de radionuclídeos em rejeitos de média e baixa atividades do reator IEA-R1. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-25112013-155403/ ;

Chicago Manual of Style (16th Edition):

Taddei, Maria Helena Tirollo. “Determinação de fatores de escala para estimativa do inventário de radionuclídeos em rejeitos de média e baixa atividades do reator IEA-R1.” 2013. Doctoral Dissertation, University of São Paulo. Accessed June 20, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-25112013-155403/ ;.

MLA Handbook (7th Edition):

Taddei, Maria Helena Tirollo. “Determinação de fatores de escala para estimativa do inventário de radionuclídeos em rejeitos de média e baixa atividades do reator IEA-R1.” 2013. Web. 20 Jun 2019.

Vancouver:

Taddei MHT. Determinação de fatores de escala para estimativa do inventário de radionuclídeos em rejeitos de média e baixa atividades do reator IEA-R1. [Internet] [Doctoral dissertation]. University of São Paulo; 2013. [cited 2019 Jun 20]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-25112013-155403/ ;.

Council of Science Editors:

Taddei MHT. Determinação de fatores de escala para estimativa do inventário de radionuclídeos em rejeitos de média e baixa atividades do reator IEA-R1. [Doctoral Dissertation]. University of São Paulo; 2013. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-25112013-155403/ ;


University of Tennessee – Knoxville

10. Griswold, Justin Reed. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.

Degree: MS, Nuclear Engineering, 2014, University of Tennessee – Knoxville

  Actinium-225 is one of the more effective radioisotopes used in alpha radioimmunotherapy. Due to its ten-day half-life, it is more efficient to create its… (more)

Subjects/Keywords: Nuclear; Nuclear Engineering

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APA (6th Edition):

Griswold, J. R. (2014). Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. (Thesis). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_gradthes/2820

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):

Griswold, Justin Reed. “Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.” 2014. Thesis, University of Tennessee – Knoxville. Accessed June 20, 2019. https://trace.tennessee.edu/utk_gradthes/2820.

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

MLA Handbook (7th Edition):

Griswold, Justin Reed. “Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232.” 2014. Web. 20 Jun 2019.

Vancouver:

Griswold JR. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. [Internet] [Thesis]. University of Tennessee – Knoxville; 2014. [cited 2019 Jun 20]. Available from: https://trace.tennessee.edu/utk_gradthes/2820.

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

Council of Science Editors:

Griswold JR. Thick Target Yield of Th-229 via Low Energy Proton Bombardment of Th-232. [Thesis]. University of Tennessee – Knoxville; 2014. Available from: https://trace.tennessee.edu/utk_gradthes/2820

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

11. Silva, Alexandre Fonseca Póvoa da. Calibração da potência do reator IPEN/MB-01 na configuração cilíndrica de menor excesso de reatividade obtida a partir da medida absoluta do fluxo médio de nêutrons.

Degree: Mestrado, Tecnologia Nuclear - Reatores, 2014, University of São Paulo

A ativação de folhas de ouro é uma das técnicas mais usadas para obter dados experimentais e assim comparar os resultados obtidos com aqueles calculados… (more)

Subjects/Keywords: calibração de potência; canais nucleares; fluxo de nêutrons térmicos; folhas de ouro; gold foils; nuclear channels; power calibration; reactor IPEN/MB-01; reator IPEN/MB-01; termal neutron flux

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APA (6th Edition):

Silva, A. F. P. d. (2014). Calibração da potência do reator IPEN/MB-01 na configuração cilíndrica de menor excesso de reatividade obtida a partir da medida absoluta do fluxo médio de nêutrons. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08102014-084019/ ;

Chicago Manual of Style (16th Edition):

Silva, Alexandre Fonseca Póvoa da. “Calibração da potência do reator IPEN/MB-01 na configuração cilíndrica de menor excesso de reatividade obtida a partir da medida absoluta do fluxo médio de nêutrons.” 2014. Masters Thesis, University of São Paulo. Accessed June 20, 2019. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08102014-084019/ ;.

MLA Handbook (7th Edition):

Silva, Alexandre Fonseca Póvoa da. “Calibração da potência do reator IPEN/MB-01 na configuração cilíndrica de menor excesso de reatividade obtida a partir da medida absoluta do fluxo médio de nêutrons.” 2014. Web. 20 Jun 2019.

Vancouver:

Silva AFPd. Calibração da potência do reator IPEN/MB-01 na configuração cilíndrica de menor excesso de reatividade obtida a partir da medida absoluta do fluxo médio de nêutrons. [Internet] [Masters thesis]. University of São Paulo; 2014. [cited 2019 Jun 20]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08102014-084019/ ;.

Council of Science Editors:

Silva AFPd. Calibração da potência do reator IPEN/MB-01 na configuração cilíndrica de menor excesso de reatividade obtida a partir da medida absoluta do fluxo médio de nêutrons. [Masters Thesis]. University of São Paulo; 2014. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08102014-084019/ ;

12. Antonio Juscelino Pinto. SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1.

Degree: Master, 2010, Centro de Desenvolvimento da Tecnologia Nuclear

O reator nuclear de pesquisa TRIGA IPR-R1 Mark I, do Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), é um reator do tipo piscina refrigerado à… (more)

Subjects/Keywords: Reator triga; Simuladores; Sistemas digitais; Instrumentação reatores; Sistemas de controle de reatores; Triga Brazil reactor; Simulators; Digital systems; Reactor instrumentation; Reactor control systems; LabView; ENGENHARIA NUCLEAR

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APA (6th Edition):

Pinto, A. J. (2010). SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1. (Masters Thesis). Centro de Desenvolvimento da Tecnologia Nuclear. Retrieved from http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=137 ;

Chicago Manual of Style (16th Edition):

Pinto, Antonio Juscelino. “SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1.” 2010. Masters Thesis, Centro de Desenvolvimento da Tecnologia Nuclear. Accessed June 20, 2019. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=137 ;.

MLA Handbook (7th Edition):

Pinto, Antonio Juscelino. “SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1.” 2010. Web. 20 Jun 2019.

Vancouver:

Pinto AJ. SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1. [Internet] [Masters thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2010. [cited 2019 Jun 20]. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=137 ;.

Council of Science Editors:

Pinto AJ. SISTEMA DIGITAL PARA SIMULAÇÃO DOS PARÂMETROS NEUTRÔNICOS DO REATOR NUCLEAR DE PESQUISA TRIGA IPR-1. [Masters Thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2010. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=137 ;

13. Flores, Pedro Tiago Marques. Análise de um projecto de investimento na energia nuclear em Portugal.

Degree: 2011, RCAAP

 Face ao aumento do consumo anual de electricidade verificado em Portugal e ao aumento dos preços dos combustíveis fósseis, é imperativo diversificar as fontes de… (more)

Subjects/Keywords: Tecnologia nuclear; Energia nuclear

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APA (6th Edition):

Flores, P. T. M. (2011). Análise de um projecto de investimento na energia nuclear em Portugal. (Thesis). RCAAP. Retrieved from https://www.rcaap.pt/detail.jsp?id=oai:ubibliorum.ubi.pt:10400.6/2399

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):

Flores, Pedro Tiago Marques. “Análise de um projecto de investimento na energia nuclear em Portugal.” 2011. Thesis, RCAAP. Accessed June 20, 2019. https://www.rcaap.pt/detail.jsp?id=oai:ubibliorum.ubi.pt:10400.6/2399.

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

MLA Handbook (7th Edition):

Flores, Pedro Tiago Marques. “Análise de um projecto de investimento na energia nuclear em Portugal.” 2011. Web. 20 Jun 2019.

Vancouver:

Flores PTM. Análise de um projecto de investimento na energia nuclear em Portugal. [Internet] [Thesis]. RCAAP; 2011. [cited 2019 Jun 20]. Available from: https://www.rcaap.pt/detail.jsp?id=oai:ubibliorum.ubi.pt:10400.6/2399.

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

Council of Science Editors:

Flores PTM. Análise de um projecto de investimento na energia nuclear em Portugal. [Thesis]. RCAAP; 2011. Available from: https://www.rcaap.pt/detail.jsp?id=oai:ubibliorum.ubi.pt:10400.6/2399

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


Texas A&M University

14. Ragusa, Jean Concetto. Accelerator driven production of tritium: target and blanket design.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Tritium is an essential component of thermonuclear weapons in the US arsenal. Unfortunately, tritium is a radioactive form of hydrogen, and one-half of the inventory… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ragusa, J. C. (2012). Accelerator driven production of tritium: target and blanket design. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34

Chicago Manual of Style (16th Edition):

Ragusa, Jean Concetto. “Accelerator driven production of tritium: target and blanket design.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34.

MLA Handbook (7th Edition):

Ragusa, Jean Concetto. “Accelerator driven production of tritium: target and blanket design.” 2012. Web. 20 Jun 2019.

Vancouver:

Ragusa JC. Accelerator driven production of tritium: target and blanket design. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34.

Council of Science Editors:

Ragusa JC. Accelerator driven production of tritium: target and blanket design. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R34


Texas A&M University

15. Ramone, Gilles Lionel. A Transport Synthetic Acceleration method for transport iterations.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 We present a family of Transport Synthetic Acceleration (TSA) methods to iteratively solve within-group scattering problems. A single iteration in these schemes consists of a… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Ramone, G. L. (2012). A Transport Synthetic Acceleration method for transport iterations. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365

Chicago Manual of Style (16th Edition):

Ramone, Gilles Lionel. “A Transport Synthetic Acceleration method for transport iterations.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365.

MLA Handbook (7th Edition):

Ramone, Gilles Lionel. “A Transport Synthetic Acceleration method for transport iterations.” 2012. Web. 20 Jun 2019.

Vancouver:

Ramone GL. A Transport Synthetic Acceleration method for transport iterations. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365.

Council of Science Editors:

Ramone GL. A Transport Synthetic Acceleration method for transport iterations. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R365


Texas A&M University

16. Reyes, Joseph Patrick. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The modeling of the complex thermal hydraulics of reactor systems involves the use of experimental test systems as well as numerical codes. A simulation of… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Reyes, J. P. (2012). Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49

Chicago Manual of Style (16th Edition):

Reyes, Joseph Patrick. “Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49.

MLA Handbook (7th Edition):

Reyes, Joseph Patrick. “Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE.” 2012. Web. 20 Jun 2019.

Vancouver:

Reyes JP. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49.

Council of Science Editors:

Reyes JP. Simulation of condensation in the presence of noncondensible gases using the French Thermal Hydraulic computer code CATHARE. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-R49


Texas A&M University

17. Troshko, Andrey Arthurovich. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Assessment of the ability of thermal hydraulic codes to correctly predict complex phenomena during reactor transients can be performed only by means of comparison against… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Troshko, A. A. (2012). Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76

Chicago Manual of Style (16th Edition):

Troshko, Andrey Arthurovich. “Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76.

MLA Handbook (7th Edition):

Troshko, Andrey Arthurovich. “Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7.” 2012. Web. 20 Jun 2019.

Vancouver:

Troshko AA. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76.

Council of Science Editors:

Troshko AA. Simulation of the loss of the residual heat removal of an integral test facility using computer code Cathare7. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-T76


Texas A&M University

18. Walkowicz, Joshua Peter. Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Thermoluminescent dosimetry is one of the most popular methods in use today for the monitoring of personnel exposures to radiation. This research investigates a different… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Walkowicz, J. P. (2012). Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355

Chicago Manual of Style (16th Edition):

Walkowicz, Joshua Peter. “Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355.

MLA Handbook (7th Edition):

Walkowicz, Joshua Peter. “Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form.” 2012. Web. 20 Jun 2019.

Vancouver:

Walkowicz JP. Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355.

Council of Science Editors:

Walkowicz JP. Investigation of a thermoluminescent dosimeter mixture between LiF:Mg,Ti and Li2B4O7 in a solid form. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-W355


Texas A&M University

19. Dixon, John Leslie. Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 This thesis presents an initial investigation of using electrostatic coalescence as an alternative to conventional separation processes to purify used automotive crankcase oil. Specific emphasis… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Dixon, J. L. (2012). Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59

Chicago Manual of Style (16th Edition):

Dixon, John Leslie. “Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59.

MLA Handbook (7th Edition):

Dixon, John Leslie. “Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes.” 2012. Web. 20 Jun 2019.

Vancouver:

Dixon JL. Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59.

Council of Science Editors:

Dixon JL. Electrostatic coalescence of used automotive crankcase oil as an alternative to other separation processes. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-D59


Texas A&M University

20. Hamm, Trenton Allen. A steady state analysis code for prediction of behavior in loop heat pipes.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The purpose of this work is to prepare an analysis raphics. code for the prediction of Loop Heat Pipe (LHP) behavior in steady-state operation. The… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Hamm, T. A. (2012). A steady state analysis code for prediction of behavior in loop heat pipes. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354

Chicago Manual of Style (16th Edition):

Hamm, Trenton Allen. “A steady state analysis code for prediction of behavior in loop heat pipes.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354.

MLA Handbook (7th Edition):

Hamm, Trenton Allen. “A steady state analysis code for prediction of behavior in loop heat pipes.” 2012. Web. 20 Jun 2019.

Vancouver:

Hamm TA. A steady state analysis code for prediction of behavior in loop heat pipes. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354.

Council of Science Editors:

Hamm TA. A steady state analysis code for prediction of behavior in loop heat pipes. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H354


Texas A&M University

21. Hari, Sridhar. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Simulations for two series of anticipated transients phics. without scram (ATWS) events have been carried out for a small, hypothetical, research reactor based on the… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Hari, S. (2012). Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373

Chicago Manual of Style (16th Edition):

Hari, Sridhar. “Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373.

MLA Handbook (7th Edition):

Hari, Sridhar. “Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program.” 2012. Web. 20 Jun 2019.

Vancouver:

Hari S. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373.

Council of Science Editors:

Hari S. Analysis of a research reactor under anticipated transients without scram events using the RELAP5/MOD3.2 computer program. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1998-THESIS-H373


Texas A&M University

22. Dorsey, Daniel John. Electrical resistance of gases in explosive magnetic flux compression generator environments.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Gases that are electrical insulators at STP can become conductors when subjected to the high pressure and temperature environment in explosive magnetic flux compression generators… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Dorsey, D. J. (2012). Electrical resistance of gases in explosive magnetic flux compression generator environments. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68

Chicago Manual of Style (16th Edition):

Dorsey, Daniel John. “Electrical resistance of gases in explosive magnetic flux compression generator environments.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68.

MLA Handbook (7th Edition):

Dorsey, Daniel John. “Electrical resistance of gases in explosive magnetic flux compression generator environments.” 2012. Web. 20 Jun 2019.

Vancouver:

Dorsey DJ. Electrical resistance of gases in explosive magnetic flux compression generator environments. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68.

Council of Science Editors:

Dorsey DJ. Electrical resistance of gases in explosive magnetic flux compression generator environments. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-D68


Texas A&M University

23. Fu, Chun. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A RELAP5/MOD3.2 model of a VVER-1000/MODEL V320 nuclear power plant, Balakovo Unit 4, was updated, improved and validated on the basis of an input deck… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Fu, C. (2012). RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8

Chicago Manual of Style (16th Edition):

Fu, Chun. “RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8.

MLA Handbook (7th Edition):

Fu, Chun. “RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel.” 2012. Web. 20 Jun 2019.

Vancouver:

Fu C. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8.

Council of Science Editors:

Fu C. RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-2000-THESIS-F8


Texas A&M University

24. Carlisle, Bruce Scott. An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 Though both film and video radiographic image techniques are available in neutron radiography, radiographic cameras are commonly used to capture the dynamic flow patterns in… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Carlisle, B. S. (2012). An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283

Chicago Manual of Style (16th Edition):

Carlisle, Bruce Scott. “An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283.

MLA Handbook (7th Edition):

Carlisle, Bruce Scott. “An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids.” 2012. Web. 20 Jun 2019.

Vancouver:

Carlisle BS. An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283.

Council of Science Editors:

Carlisle BS. An evaluation of the neutron radiography facility at the Nuclear Science Center for dynamic imaging of two-phase hydrogenous fluids. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C283


Texas A&M University

25. Castrianni, Christopher Lee. A one-dimensional nonlinear corner balance method for solving the neutron transport equation.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The one-dimensional nonlinear comer balance method is a new spatial discretization scheme for solving the transport equation on grids consisting of arbitrarily connected polygonal meshes.… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Castrianni, C. L. (2012). A one-dimensional nonlinear corner balance method for solving the neutron transport equation. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355

Chicago Manual of Style (16th Edition):

Castrianni, Christopher Lee. “A one-dimensional nonlinear corner balance method for solving the neutron transport equation.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355.

MLA Handbook (7th Edition):

Castrianni, Christopher Lee. “A one-dimensional nonlinear corner balance method for solving the neutron transport equation.” 2012. Web. 20 Jun 2019.

Vancouver:

Castrianni CL. A one-dimensional nonlinear corner balance method for solving the neutron transport equation. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355.

Council of Science Editors:

Castrianni CL. A one-dimensional nonlinear corner balance method for solving the neutron transport equation. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C355


Texas A&M University

26. Cebull, Peter Patrick. Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A small-break loss-of-coolant accident experiment conducted at the PMK-2 integral test facility in Hungary is analyzed using the RELAP5/MOD3.1 thermal-hydrauhc code. The experiment simulated a… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Cebull, P. P. (2012). Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875

Chicago Manual of Style (16th Edition):

Cebull, Peter Patrick. “Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875.

MLA Handbook (7th Edition):

Cebull, Peter Patrick. “Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1.” 2012. Web. 20 Jun 2019.

Vancouver:

Cebull PP. Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875.

Council of Science Editors:

Cebull PP. Simulation of the SPE-4 small-break loss-of-coolant accident using RELAP5/MOD 3.1. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C3875


Texas A&M University

27. Costes, Sylvain Vincent. Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 This study concerns with the development of a simple three-dimensional technique to determine the velocity of fluid by tracing the motion of seeded particles in… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Costes, S. V. (2012). Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842

Chicago Manual of Style (16th Edition):

Costes, Sylvain Vincent. “Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842.

MLA Handbook (7th Edition):

Costes, Sylvain Vincent. “Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions.” 2012. Web. 20 Jun 2019.

Vancouver:

Costes SV. Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842.

Council of Science Editors:

Costes SV. Development of a three-dimensional particle image velocimetry algorithm and analysis of synthetic and experimental flows in three-dimensions. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-C842


Texas A&M University

28. Eaton, Thomas Lance. A generalized simple corner-balance transport method for 1-D problems.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 A new generalized simple Comer Balance transport method was developed in an attempt to produce accurate solutions to all one-dimensional transport problems. The method allows… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Eaton, T. L. (2012). A generalized simple corner-balance transport method for 1-D problems. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145

Chicago Manual of Style (16th Edition):

Eaton, Thomas Lance. “A generalized simple corner-balance transport method for 1-D problems.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145.

MLA Handbook (7th Edition):

Eaton, Thomas Lance. “A generalized simple corner-balance transport method for 1-D problems.” 2012. Web. 20 Jun 2019.

Vancouver:

Eaton TL. A generalized simple corner-balance transport method for 1-D problems. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145.

Council of Science Editors:

Eaton TL. A generalized simple corner-balance transport method for 1-D problems. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1994-THESIS-E145


Texas A&M University

29. Yoon, Churl. Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 The Particle Image Velocimetry (plV) flow measu rement technique is a very efficient technique for studying the structure of various fluid flows. It provides quantitative… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Yoon, C. (2012). Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66

Chicago Manual of Style (16th Edition):

Yoon, Churl. “Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66.

MLA Handbook (7th Edition):

Yoon, Churl. “Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models.” 2012. Web. 20 Jun 2019.

Vancouver:

Yoon C. Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66.

Council of Science Editors:

Yoon C. Development of a genetic algorithm tracking technique for the particle image velocimetry and comparison with other tracking models. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1996-THESIS-Y66


Texas A&M University

30. Caldwell, Amy Baker. Risk analysis of shipping plutonium pits and mixed oxide fuel.

Degree: MS, nuclear engineering, 2012, Texas A&M University

 With the end of the cold war, there no longer seems to be a credible threat of war between nuclear superpowers, with its possible consequence… (more)

Subjects/Keywords: nuclear engineering.; Major nuclear engineering.

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APA (6th Edition):

Caldwell, A. B. (2012). Risk analysis of shipping plutonium pits and mixed oxide fuel. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35

Chicago Manual of Style (16th Edition):

Caldwell, Amy Baker. “Risk analysis of shipping plutonium pits and mixed oxide fuel.” 2012. Masters Thesis, Texas A&M University. Accessed June 20, 2019. http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35.

MLA Handbook (7th Edition):

Caldwell, Amy Baker. “Risk analysis of shipping plutonium pits and mixed oxide fuel.” 2012. Web. 20 Jun 2019.

Vancouver:

Caldwell AB. Risk analysis of shipping plutonium pits and mixed oxide fuel. [Internet] [Masters thesis]. Texas A&M University; 2012. [cited 2019 Jun 20]. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35.

Council of Science Editors:

Caldwell AB. Risk analysis of shipping plutonium pits and mixed oxide fuel. [Masters Thesis]. Texas A&M University; 2012. Available from: http://hdl.handle.net/1969.1/ETD-TAMU-1997-THESIS-C35

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