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You searched for subject:(PWR). Showing records 1 – 30 of 155 total matches.

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Uppsala University

1. Nordlander, Joakim. Utvärdering av dimensionell stabilitet i PWR-patroner i Ringhals.

Degree: Applied Nuclear Physics, 2015, Uppsala University

  Dimensional stability is an important aspect of fuel mechanical design and licensing of new fuel designs for nuclear power plants. Dimensional changes within the… (more)

Subjects/Keywords: PWR; Ringhals; Rod bow; PWR; Ringhals; Stavböjning

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

APA (6th Edition):

Nordlander, J. (2015). Utvärdering av dimensionell stabilitet i PWR-patroner i Ringhals. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-256948

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):

Nordlander, Joakim. “Utvärdering av dimensionell stabilitet i PWR-patroner i Ringhals.” 2015. Thesis, Uppsala University. Accessed April 14, 2021. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-256948.

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

MLA Handbook (7th Edition):

Nordlander, Joakim. “Utvärdering av dimensionell stabilitet i PWR-patroner i Ringhals.” 2015. Web. 14 Apr 2021.

Vancouver:

Nordlander J. Utvärdering av dimensionell stabilitet i PWR-patroner i Ringhals. [Internet] [Thesis]. Uppsala University; 2015. [cited 2021 Apr 14]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-256948.

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

Council of Science Editors:

Nordlander J. Utvärdering av dimensionell stabilitet i PWR-patroner i Ringhals. [Thesis]. Uppsala University; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-256948

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


Texas A&M University

2. Kyriakopoulos, Vasileios. Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed.

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

 This thesis examines five chemical solutions that are considered to be representative of the solution created in the containment sump during a postulated LOCA (loss… (more)

Subjects/Keywords: GSI-191; strainer; PWR; nuclear

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APA (6th Edition):

Kyriakopoulos, V. (2016). Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed. (Masters Thesis). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/159105

Chicago Manual of Style (16th Edition):

Kyriakopoulos, Vasileios. “Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed.” 2016. Masters Thesis, Texas A&M University. Accessed April 14, 2021. http://hdl.handle.net/1969.1/159105.

MLA Handbook (7th Edition):

Kyriakopoulos, Vasileios. “Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed.” 2016. Web. 14 Apr 2021.

Vancouver:

Kyriakopoulos V. Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed. [Internet] [Masters thesis]. Texas A&M University; 2016. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/1969.1/159105.

Council of Science Editors:

Kyriakopoulos V. Effect of Chemical Injections on Pressure Drop through a Fibrous Debris Bed. [Masters Thesis]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/159105


Pontifical Catholic University of Rio de Janeiro

3. JORGE ALEXANDRE ONODA PESSANHA. [en] ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2.

Degree: 2018, Pontifical Catholic University of Rio de Janeiro

[pt] No projeto de uma usina nuclear PWR, é necessário verificar se os limites de projeto dos seus componentes são respeitados mesmo em condições de… (more)

Subjects/Keywords: [pt] USINA NUCLEAR PWR; [en] PWR NUCLEAR PLANT; [pt] SIMULACAO DE TRANSITORIOS EM PWR; [en] SIMULATION IN TRANSIENTS IN PWR

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APA (6th Edition):

PESSANHA, J. A. O. (2018). [en] ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2. (Thesis). Pontifical Catholic University of Rio de Janeiro. Retrieved from http://www.maxwell.vrac.puc-rio.br/Busca_etds.php?strSecao=resultado&nrSeq=33542

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):

PESSANHA, JORGE ALEXANDRE ONODA. “[en] ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2.” 2018. Thesis, Pontifical Catholic University of Rio de Janeiro. Accessed April 14, 2021. http://www.maxwell.vrac.puc-rio.br/Busca_etds.php?strSecao=resultado&nrSeq=33542.

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

MLA Handbook (7th Edition):

PESSANHA, JORGE ALEXANDRE ONODA. “[en] ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2.” 2018. Web. 14 Apr 2021.

Vancouver:

PESSANHA JAO. [en] ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2. [Internet] [Thesis]. Pontifical Catholic University of Rio de Janeiro; 2018. [cited 2021 Apr 14]. Available from: http://www.maxwell.vrac.puc-rio.br/Busca_etds.php?strSecao=resultado&nrSeq=33542.

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

Council of Science Editors:

PESSANHA JAO. [en] ANALYSIS OF DYNAMIC BEHAVIOR OF A PWR UTILIZING THE COMPUTER PROGRAM SARDAN 2. [Thesis]. Pontifical Catholic University of Rio de Janeiro; 2018. Available from: http://www.maxwell.vrac.puc-rio.br/Busca_etds.php?strSecao=resultado&nrSeq=33542

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


Universitat Politècnica de València

4. Querol Vives, Andrea. Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado.

Degree: 2016, Universitat Politècnica de València

 [EN] The origin of the scaling-issue is the impossibility to obtain measured data in case of an accident in nuclear reactors. The knowledge of thermal… (more)

Subjects/Keywords: TRACE5; LSTF; PKL; PWR; Termohidráulica

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APA (6th Edition):

Querol Vives, A. (2016). Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado. (Doctoral Dissertation). Universitat Politècnica de València. Retrieved from http://hdl.handle.net/10251/59445

Chicago Manual of Style (16th Edition):

Querol Vives, Andrea. “Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado. ” 2016. Doctoral Dissertation, Universitat Politècnica de València. Accessed April 14, 2021. http://hdl.handle.net/10251/59445.

MLA Handbook (7th Edition):

Querol Vives, Andrea. “Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado. ” 2016. Web. 14 Apr 2021.

Vancouver:

Querol Vives A. Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado. [Internet] [Doctoral dissertation]. Universitat Politècnica de València; 2016. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/10251/59445.

Council of Science Editors:

Querol Vives A. Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado. [Doctoral Dissertation]. Universitat Politècnica de València; 2016. Available from: http://hdl.handle.net/10251/59445


California State University – Chico

5. Barnett, Susan. Participants' Perceptions of the Barriers to Adopting Innovation: A Case Study of the AKR-PWR Centennial Workshop .

Degree: 2011, California State University – Chico

 ABSTRACT PARTICIPANTS??? PERCEPTIONS OF THE BARRIERS TO ADOPTING INNOVATION: A CASE STUDY OF THE AKR-PWR CENTENNIAL WORKSHOP by Susan Barnett Master of Arts in Recreation… (more)

Subjects/Keywords: AKR-PWR Centennial Workshop

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APA (6th Edition):

Barnett, S. (2011). Participants' Perceptions of the Barriers to Adopting Innovation: A Case Study of the AKR-PWR Centennial Workshop . (Thesis). California State University – Chico. Retrieved from http://hdl.handle.net/10211.4/259

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):

Barnett, Susan. “Participants' Perceptions of the Barriers to Adopting Innovation: A Case Study of the AKR-PWR Centennial Workshop .” 2011. Thesis, California State University – Chico. Accessed April 14, 2021. http://hdl.handle.net/10211.4/259.

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

MLA Handbook (7th Edition):

Barnett, Susan. “Participants' Perceptions of the Barriers to Adopting Innovation: A Case Study of the AKR-PWR Centennial Workshop .” 2011. Web. 14 Apr 2021.

Vancouver:

Barnett S. Participants' Perceptions of the Barriers to Adopting Innovation: A Case Study of the AKR-PWR Centennial Workshop . [Internet] [Thesis]. California State University – Chico; 2011. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/10211.4/259.

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

Council of Science Editors:

Barnett S. Participants' Perceptions of the Barriers to Adopting Innovation: A Case Study of the AKR-PWR Centennial Workshop . [Thesis]. California State University – Chico; 2011. Available from: http://hdl.handle.net/10211.4/259

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

6. Pedro, Miguel António de Morais. Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal.

Degree: 2012, Repositório Científico do Instituto Politécnico de Lisboa

 O presente trabalho tem como objectivo avaliar economicamente e determinar a viabilidade da implementação de um reactor nuclear para produção de energia eléctrica. Faz-se uma… (more)

Subjects/Keywords: Avaliação económica; Energia nuclear; Reactor PWR

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APA (6th Edition):

Pedro, M. A. d. M. (2012). Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal. (Thesis). Repositório Científico do Instituto Politécnico de Lisboa. Retrieved from http://www.rcaap.pt/detail.jsp?id=oai:repositorio.ipl.pt:10400.21/2167

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):

Pedro, Miguel António de Morais. “Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal.” 2012. Thesis, Repositório Científico do Instituto Politécnico de Lisboa. Accessed April 14, 2021. http://www.rcaap.pt/detail.jsp?id=oai:repositorio.ipl.pt:10400.21/2167.

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

MLA Handbook (7th Edition):

Pedro, Miguel António de Morais. “Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal.” 2012. Web. 14 Apr 2021.

Vancouver:

Pedro MAdM. Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal. [Internet] [Thesis]. Repositório Científico do Instituto Politécnico de Lisboa; 2012. [cited 2021 Apr 14]. Available from: http://www.rcaap.pt/detail.jsp?id=oai:repositorio.ipl.pt:10400.21/2167.

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

Council of Science Editors:

Pedro MAdM. Viabilidade económica da implementação de um reactor nuclear para a produção de energia eléctrica em Portugal. [Thesis]. Repositório Científico do Instituto Politécnico de Lisboa; 2012. Available from: http://www.rcaap.pt/detail.jsp?id=oai:repositorio.ipl.pt:10400.21/2167

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


Cranfield University

7. Meng, Fanliang. Actuation system design with electrically powered actuators.

Degree: MSc by Research, 2011, Cranfield University

 This project addresses the actuation system architecture of future All-electric aircraft (AEA) with electrically powered actuators (EPA). Firstly, the information of EPAs is reviewed, and… (more)

Subjects/Keywords: EHA; EHA; conventional; distributed; architecture; PWR

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APA (6th Edition):

Meng, F. (2011). Actuation system design with electrically powered actuators. (Masters Thesis). Cranfield University. Retrieved from http://dspace.lib.cranfield.ac.uk/handle/1826/6282

Chicago Manual of Style (16th Edition):

Meng, Fanliang. “Actuation system design with electrically powered actuators.” 2011. Masters Thesis, Cranfield University. Accessed April 14, 2021. http://dspace.lib.cranfield.ac.uk/handle/1826/6282.

MLA Handbook (7th Edition):

Meng, Fanliang. “Actuation system design with electrically powered actuators.” 2011. Web. 14 Apr 2021.

Vancouver:

Meng F. Actuation system design with electrically powered actuators. [Internet] [Masters thesis]. Cranfield University; 2011. [cited 2021 Apr 14]. Available from: http://dspace.lib.cranfield.ac.uk/handle/1826/6282.

Council of Science Editors:

Meng F. Actuation system design with electrically powered actuators. [Masters Thesis]. Cranfield University; 2011. Available from: http://dspace.lib.cranfield.ac.uk/handle/1826/6282

8. ROSA, José Eduardo Pereira da. Simulação computacional da homogeneização do ácido bórico em pressurizador de um reator nuclear avançado.

Degree: 2013, Brazil

Submitted by Almir Azevedo ([email protected]) on 2013-12-04T12:50:22Z No. of bitstreams: 1 dissertacao_mestrado_ien_2013_05.pdf: 1528233 bytes, checksum: f68d87785bc45e2f76ceb65d2ba1ef23 (MD5)

Made available in DSpace on 2013-12-04T12:50:22Z (GMT). No.… (more)

Subjects/Keywords: Reator PWR; Dinâmica de fluido computacional; pressurizadores

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APA (6th Edition):

ROSA, J. E. P. d. (2013). Simulação computacional da homogeneização do ácido bórico em pressurizador de um reator nuclear avançado. (Masters Thesis). Brazil. Retrieved from http://hdl.handle.net/ien/532

Chicago Manual of Style (16th Edition):

ROSA, José Eduardo Pereira da. “Simulação computacional da homogeneização do ácido bórico em pressurizador de um reator nuclear avançado.” 2013. Masters Thesis, Brazil. Accessed April 14, 2021. http://hdl.handle.net/ien/532.

MLA Handbook (7th Edition):

ROSA, José Eduardo Pereira da. “Simulação computacional da homogeneização do ácido bórico em pressurizador de um reator nuclear avançado.” 2013. Web. 14 Apr 2021.

Vancouver:

ROSA JEPd. Simulação computacional da homogeneização do ácido bórico em pressurizador de um reator nuclear avançado. [Internet] [Masters thesis]. Brazil; 2013. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/ien/532.

Council of Science Editors:

ROSA JEPd. Simulação computacional da homogeneização do ácido bórico em pressurizador de um reator nuclear avançado. [Masters Thesis]. Brazil; 2013. Available from: http://hdl.handle.net/ien/532

9. CUNHA, Caio Július César Miranda Rodrigues da. Análise termohidráulica de um conjunto combustível do reator AP1000 com o uso de óxidos mistos de U/Th.

Degree: 2019, Federal University of Pernambuco

CAPES

O cenário energético brasileiro está passando por mudanças desde os últimos cinco anos, no qual, as fontes renováveis de energia estão exercendo uma participação… (more)

Subjects/Keywords: Engenharia nuclear; AP1000; PWR; Tório; Termohidráulica; CFX

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APA (6th Edition):

CUNHA, C. J. C. M. R. d. (2019). Análise termohidráulica de um conjunto combustível do reator AP1000 com o uso de óxidos mistos de U/Th. (Masters Thesis). Federal University of Pernambuco. Retrieved from https://repositorio.ufpe.br/handle/123456789/35443

Chicago Manual of Style (16th Edition):

CUNHA, Caio Július César Miranda Rodrigues da. “Análise termohidráulica de um conjunto combustível do reator AP1000 com o uso de óxidos mistos de U/Th.” 2019. Masters Thesis, Federal University of Pernambuco. Accessed April 14, 2021. https://repositorio.ufpe.br/handle/123456789/35443.

MLA Handbook (7th Edition):

CUNHA, Caio Július César Miranda Rodrigues da. “Análise termohidráulica de um conjunto combustível do reator AP1000 com o uso de óxidos mistos de U/Th.” 2019. Web. 14 Apr 2021.

Vancouver:

CUNHA CJCMRd. Análise termohidráulica de um conjunto combustível do reator AP1000 com o uso de óxidos mistos de U/Th. [Internet] [Masters thesis]. Federal University of Pernambuco; 2019. [cited 2021 Apr 14]. Available from: https://repositorio.ufpe.br/handle/123456789/35443.

Council of Science Editors:

CUNHA CJCMRd. Análise termohidráulica de um conjunto combustível do reator AP1000 com o uso de óxidos mistos de U/Th. [Masters Thesis]. Federal University of Pernambuco; 2019. Available from: https://repositorio.ufpe.br/handle/123456789/35443

10. Fabio Abud Mansur. Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2.

Degree: Master, 2015, Centro de Desenvolvimento da Tecnologia Nuclear

A liga 800GN (grau nuclear) é um material utilizado na fabricação de geradores de vapor para reatores de água pressurizada (PWR) de usinas nucleares devido… (more)

Subjects/Keywords: Corrosão; Corrosão por pites; Reatores PWR; Corrosion; Incoloy 800; Pitting corrosion; PWR Reactor; CORROSAO

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APA (6th Edition):

Mansur, F. A. (2015). Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2. (Masters Thesis). Centro de Desenvolvimento da Tecnologia Nuclear. Retrieved from http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=340 ;

Chicago Manual of Style (16th Edition):

Mansur, Fabio Abud. “Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2.” 2015. Masters Thesis, Centro de Desenvolvimento da Tecnologia Nuclear. Accessed April 14, 2021. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=340 ;.

MLA Handbook (7th Edition):

Mansur, Fabio Abud. “Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2.” 2015. Web. 14 Apr 2021.

Vancouver:

Mansur FA. Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2. [Internet] [Masters thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2015. [cited 2021 Apr 14]. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=340 ;.

Council of Science Editors:

Mansur FA. Corrosão de liga 800GN em ambiente do circuito secundário da Central Nuclear de Angra 2. [Masters Thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2015. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=340 ;


Brno University of Technology

11. Michalica, Martin. Parogenerátory tlakovodních reaktorů: Steam Generators of PWR.

Degree: 2019, Brno University of Technology

 This bachelors thesis describes various designs of steam generators. The first part of the thesis describes the beginning of the nuclear industry in Russia. The… (more)

Subjects/Keywords: Parogenerátor; VVER-1000; PWR; historie; 3D model; Steam generator; VVER-1000 PWR; history; 3D model

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APA (6th Edition):

Michalica, M. (2019). Parogenerátory tlakovodních reaktorů: Steam Generators of PWR. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/41434

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):

Michalica, Martin. “Parogenerátory tlakovodních reaktorů: Steam Generators of PWR.” 2019. Thesis, Brno University of Technology. Accessed April 14, 2021. http://hdl.handle.net/11012/41434.

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

MLA Handbook (7th Edition):

Michalica, Martin. “Parogenerátory tlakovodních reaktorů: Steam Generators of PWR.” 2019. Web. 14 Apr 2021.

Vancouver:

Michalica M. Parogenerátory tlakovodních reaktorů: Steam Generators of PWR. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/11012/41434.

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

Council of Science Editors:

Michalica M. Parogenerátory tlakovodních reaktorů: Steam Generators of PWR. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/41434

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

12. Marcelo Moraes dos Santos. Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto.

Degree: 2019, University of São Paulo

A melhoria nos aspectos de eficiência e de segurança dos reatores nucleares compactos está diretamente ligada às inovações nos combustíveis e na geometria dos Elementos… (more)

Subjects/Keywords: análise mecânica; elemento combustível; reatores PWR compactos; fuel element; mechanical analysis; PWR compact reactors

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APA (6th Edition):

Santos, M. M. d. (2019). Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto. (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08082019-140803/

Chicago Manual of Style (16th Edition):

Santos, Marcelo Moraes dos. “Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto.” 2019. Masters Thesis, University of São Paulo. Accessed April 14, 2021. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08082019-140803/.

MLA Handbook (7th Edition):

Santos, Marcelo Moraes dos. “Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto.” 2019. Web. 14 Apr 2021.

Vancouver:

Santos MMd. Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto. [Internet] [Masters thesis]. University of São Paulo; 2019. [cited 2021 Apr 14]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08082019-140803/.

Council of Science Editors:

Santos MMd. Avaliação estrutural de um elemento combustível do tipo placa para um reator nuclear compacto. [Masters Thesis]. University of São Paulo; 2019. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-08082019-140803/

13. Israel Gleybson Ferreira da Silva. Avaliação do desempenho de diferentes materiais de tubulação para aplicação do Leak-Before-Break (LBB).

Degree: 2019, University of São Paulo

Fundamentado na mecânica da fratura, o conceito do Leak-Before-Break (LBB) \"Vazamento Antes da Falhac̈onsidera que um vazamento proveniente de uma trinca pode ser detectado antes… (more)

Subjects/Keywords: Leak-Before-Break; material de tubulação; reator PWR; Leak-Before-Break; piping material; PWR reactor

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APA (6th Edition):

Silva, I. G. F. d. (2019). Avaliação do desempenho de diferentes materiais de tubulação para aplicação do Leak-Before-Break (LBB). (Masters Thesis). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85134/tde-03072019-152331/

Chicago Manual of Style (16th Edition):

Silva, Israel Gleybson Ferreira da. “Avaliação do desempenho de diferentes materiais de tubulação para aplicação do Leak-Before-Break (LBB).” 2019. Masters Thesis, University of São Paulo. Accessed April 14, 2021. http://www.teses.usp.br/teses/disponiveis/85/85134/tde-03072019-152331/.

MLA Handbook (7th Edition):

Silva, Israel Gleybson Ferreira da. “Avaliação do desempenho de diferentes materiais de tubulação para aplicação do Leak-Before-Break (LBB).” 2019. Web. 14 Apr 2021.

Vancouver:

Silva IGFd. Avaliação do desempenho de diferentes materiais de tubulação para aplicação do Leak-Before-Break (LBB). [Internet] [Masters thesis]. University of São Paulo; 2019. [cited 2021 Apr 14]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85134/tde-03072019-152331/.

Council of Science Editors:

Silva IGFd. Avaliação do desempenho de diferentes materiais de tubulação para aplicação do Leak-Before-Break (LBB). [Masters Thesis]. University of São Paulo; 2019. Available from: http://www.teses.usp.br/teses/disponiveis/85/85134/tde-03072019-152331/

14. Raphael Gomes de Paula. Metodologia para determinação da taxa de prorrogação de trinca por corrosão sob tensão em solda de metais dissimilares em meio simulado de Reator Nuclear PWR.

Degree: Master, 2014, Centro de Desenvolvimento da Tecnologia Nuclear

As ligas de Níquel são amplamente utilizadas na construção de diversos componentes de reatores à água pressurizada PWR. Estes materiais foram selecionados por possuírem elevada… (more)

Subjects/Keywords: Reatores PWR; Corrosão sob tensão; Trinca; Solda; PWR type reactors; Stress corrosion; Cracking; Welding; ENGENHARIA DE MATERIAIS E METALURGICA

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APA (6th Edition):

Paula, R. G. d. (2014). Metodologia para determinação da taxa de prorrogação de trinca por corrosão sob tensão em solda de metais dissimilares em meio simulado de Reator Nuclear PWR. (Masters Thesis). Centro de Desenvolvimento da Tecnologia Nuclear. Retrieved from http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=330 ;

Chicago Manual of Style (16th Edition):

Paula, Raphael Gomes de. “Metodologia para determinação da taxa de prorrogação de trinca por corrosão sob tensão em solda de metais dissimilares em meio simulado de Reator Nuclear PWR.” 2014. Masters Thesis, Centro de Desenvolvimento da Tecnologia Nuclear. Accessed April 14, 2021. http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=330 ;.

MLA Handbook (7th Edition):

Paula, Raphael Gomes de. “Metodologia para determinação da taxa de prorrogação de trinca por corrosão sob tensão em solda de metais dissimilares em meio simulado de Reator Nuclear PWR.” 2014. Web. 14 Apr 2021.

Vancouver:

Paula RGd. Metodologia para determinação da taxa de prorrogação de trinca por corrosão sob tensão em solda de metais dissimilares em meio simulado de Reator Nuclear PWR. [Internet] [Masters thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2014. [cited 2021 Apr 14]. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=330 ;.

Council of Science Editors:

Paula RGd. Metodologia para determinação da taxa de prorrogação de trinca por corrosão sob tensão em solda de metais dissimilares em meio simulado de Reator Nuclear PWR. [Masters Thesis]. Centro de Desenvolvimento da Tecnologia Nuclear; 2014. Available from: http://www.bdtd.cdtn.br//tde_busca/arquivo.php?codArquivo=330 ;


Brno University of Technology

15. Takács, Gergő. Trendy ve vývoji jaderného paliva: Trends in nuclear fuel development.

Degree: 2020, Brno University of Technology

 The aim of the bachelor thesis is to acquaint the reader with the differences between pressurized water reactors of the eastern and western type. It… (more)

Subjects/Keywords: VVER; PWR; palivový súbor; pokrytie; nároky na jadrové palivo; ATF; VVER; PWR; fuel assembly; cladding material; requirements for nuclear fuel; ATF

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APA (6th Edition):

Takács, G. (2020). Trendy ve vývoji jaderného paliva: Trends in nuclear fuel development. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/190568

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):

Takács, Gergő. “Trendy ve vývoji jaderného paliva: Trends in nuclear fuel development.” 2020. Thesis, Brno University of Technology. Accessed April 14, 2021. http://hdl.handle.net/11012/190568.

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

MLA Handbook (7th Edition):

Takács, Gergő. “Trendy ve vývoji jaderného paliva: Trends in nuclear fuel development.” 2020. Web. 14 Apr 2021.

Vancouver:

Takács G. Trendy ve vývoji jaderného paliva: Trends in nuclear fuel development. [Internet] [Thesis]. Brno University of Technology; 2020. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/11012/190568.

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

Council of Science Editors:

Takács G. Trendy ve vývoji jaderného paliva: Trends in nuclear fuel development. [Thesis]. Brno University of Technology; 2020. Available from: http://hdl.handle.net/11012/190568

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

16. Stefani, Giovanni Laranjo de. Sobre a viabilidade de conversão de um reator avançado PWR com núcleo de UO2 para (Th,U)O2.

Degree: 2017, Brazil

Orientador: Prof. Dr. José Rubens Maiorino

Tese ( doutorado)- Universidade Federal do ABC. Programa de Pós-Graduação em Energia, 2017.

O presente trabalho apresenta a análise… (more)

Subjects/Keywords: PWR AVANÇADO; MOX; TÓRIO; ADVANCED PWR; THORIUM; NUCLEAR ENERGY; PROGRAMA DE PÓS-GRADUAÇÃO EM ENERGIA - UFABC

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APA (6th Edition):

Stefani, G. L. d. (2017). Sobre a viabilidade de conversão de um reator avançado PWR com núcleo de UO2 para (Th,U)O2. (Doctoral Dissertation). Brazil. Retrieved from http://biblioteca.ufabc.edu.br/index.php?codigo_sophia=106877

Chicago Manual of Style (16th Edition):

Stefani, Giovanni Laranjo de. “Sobre a viabilidade de conversão de um reator avançado PWR com núcleo de UO2 para (Th,U)O2.” 2017. Doctoral Dissertation, Brazil. Accessed April 14, 2021. http://biblioteca.ufabc.edu.br/index.php?codigo_sophia=106877.

MLA Handbook (7th Edition):

Stefani, Giovanni Laranjo de. “Sobre a viabilidade de conversão de um reator avançado PWR com núcleo de UO2 para (Th,U)O2.” 2017. Web. 14 Apr 2021.

Vancouver:

Stefani GLd. Sobre a viabilidade de conversão de um reator avançado PWR com núcleo de UO2 para (Th,U)O2. [Internet] [Doctoral dissertation]. Brazil; 2017. [cited 2021 Apr 14]. Available from: http://biblioteca.ufabc.edu.br/index.php?codigo_sophia=106877.

Council of Science Editors:

Stefani GLd. Sobre a viabilidade de conversão de um reator avançado PWR com núcleo de UO2 para (Th,U)O2. [Doctoral Dissertation]. Brazil; 2017. Available from: http://biblioteca.ufabc.edu.br/index.php?codigo_sophia=106877


University of California – Berkeley

17. Di Sanzo, Christian Diego. Increasing fuel utilization of breed and burn reactors.

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

 Breed and Burn reactors (B&B), also referred to Traveling Wave Reactors, are fast spectrum reactors that can be fed indefinitely with depleted uranium only, once… (more)

Subjects/Keywords: Nuclear engineering; breed and burn; fast reactors; fuel utilization; PWR

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APA (6th Edition):

Di Sanzo, C. D. (2014). Increasing fuel utilization of breed and burn reactors. (Thesis). University of California – Berkeley. Retrieved from http://www.escholarship.org/uc/item/7jx5v1j4

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):

Di Sanzo, Christian Diego. “Increasing fuel utilization of breed and burn reactors.” 2014. Thesis, University of California – Berkeley. Accessed April 14, 2021. http://www.escholarship.org/uc/item/7jx5v1j4.

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

MLA Handbook (7th Edition):

Di Sanzo, Christian Diego. “Increasing fuel utilization of breed and burn reactors.” 2014. Web. 14 Apr 2021.

Vancouver:

Di Sanzo CD. Increasing fuel utilization of breed and burn reactors. [Internet] [Thesis]. University of California – Berkeley; 2014. [cited 2021 Apr 14]. Available from: http://www.escholarship.org/uc/item/7jx5v1j4.

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

Council of Science Editors:

Di Sanzo CD. Increasing fuel utilization of breed and burn reactors. [Thesis]. University of California – Berkeley; 2014. Available from: http://www.escholarship.org/uc/item/7jx5v1j4

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


University of Manchester

18. Necib Ammour, Ouarda. Effect of Platinum Group Metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors.

Degree: 2010, University of Manchester

 In pressurised water reactors (PWRs), hydrogen overpressure is used to keep the corrosion potentialbelow the threshold for onset of intergranular stress corrosion cracking (IGSCC) in… (more)

Subjects/Keywords: SCC; PGMs; 304SS; PWR

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APA (6th Edition):

Necib Ammour, O. (2010). Effect of Platinum Group Metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors. (Doctoral Dissertation). University of Manchester. Retrieved from http://www.manchester.ac.uk/escholar/uk-ac-man-scw:84669

Chicago Manual of Style (16th Edition):

Necib Ammour, Ouarda. “Effect of Platinum Group Metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors.” 2010. Doctoral Dissertation, University of Manchester. Accessed April 14, 2021. http://www.manchester.ac.uk/escholar/uk-ac-man-scw:84669.

MLA Handbook (7th Edition):

Necib Ammour, Ouarda. “Effect of Platinum Group Metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors.” 2010. Web. 14 Apr 2021.

Vancouver:

Necib Ammour O. Effect of Platinum Group Metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors. [Internet] [Doctoral dissertation]. University of Manchester; 2010. [cited 2021 Apr 14]. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:84669.

Council of Science Editors:

Necib Ammour O. Effect of Platinum Group Metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors. [Doctoral Dissertation]. University of Manchester; 2010. Available from: http://www.manchester.ac.uk/escholar/uk-ac-man-scw:84669


Penn State University

19. Shapiro, Rachel Ann. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.

Degree: 2014, Penn State University

 Fully ceramic microencapsulated (FCM) fuel is an accident tolerant design that takes advantage of TRISO technology, embedding the particles in a ceramic matrix (SiC) to… (more)

Subjects/Keywords: PWR; TRISO; accident-tolerant fuel; fully ceramic microencapsulated fuel; neutronics

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

APA (6th Edition):

Shapiro, R. A. (2014). Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. (Thesis). Penn State University. Retrieved from https://submit-etda.libraries.psu.edu/catalog/22708

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):

Shapiro, Rachel Ann. “Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.” 2014. Thesis, Penn State University. Accessed April 14, 2021. https://submit-etda.libraries.psu.edu/catalog/22708.

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

MLA Handbook (7th Edition):

Shapiro, Rachel Ann. “Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel.” 2014. Web. 14 Apr 2021.

Vancouver:

Shapiro RA. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. [Internet] [Thesis]. Penn State University; 2014. [cited 2021 Apr 14]. Available from: https://submit-etda.libraries.psu.edu/catalog/22708.

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

Council of Science Editors:

Shapiro RA. Core Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel. [Thesis]. Penn State University; 2014. Available from: https://submit-etda.libraries.psu.edu/catalog/22708

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


University of Manchester

20. Wright, David Marc. The effect of cold rolling on the susceptibility of austenitic stainless steel to stress corrosion cracking in primary circuit pressurised water reactor environment.

Degree: Thesis (Eng.D.), 2012, University of Manchester

 The stress corrosion cracking (SCC) of components which are fabricated from austenitic stainless steel has been observed in the primary circuit of pressurised water reactors… (more)

Subjects/Keywords: 620.1; SCC; Austenitic stainless steel; Cold work; PWR

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APA (6th Edition):

Wright, D. M. (2012). The effect of cold rolling on the susceptibility of austenitic stainless steel to stress corrosion cracking in primary circuit pressurised water reactor environment. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/the-effect-of-cold-rolling-on-the-susceptibility-of-austenitic-stainless-steel-to-stress-corrosion-cracking-in-primary-circuit-pressurised-water-reactor-environment(43d9ea3e-e941-4412-90f6-907f715b78c5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566548

Chicago Manual of Style (16th Edition):

Wright, David Marc. “The effect of cold rolling on the susceptibility of austenitic stainless steel to stress corrosion cracking in primary circuit pressurised water reactor environment.” 2012. Doctoral Dissertation, University of Manchester. Accessed April 14, 2021. https://www.research.manchester.ac.uk/portal/en/theses/the-effect-of-cold-rolling-on-the-susceptibility-of-austenitic-stainless-steel-to-stress-corrosion-cracking-in-primary-circuit-pressurised-water-reactor-environment(43d9ea3e-e941-4412-90f6-907f715b78c5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566548.

MLA Handbook (7th Edition):

Wright, David Marc. “The effect of cold rolling on the susceptibility of austenitic stainless steel to stress corrosion cracking in primary circuit pressurised water reactor environment.” 2012. Web. 14 Apr 2021.

Vancouver:

Wright DM. The effect of cold rolling on the susceptibility of austenitic stainless steel to stress corrosion cracking in primary circuit pressurised water reactor environment. [Internet] [Doctoral dissertation]. University of Manchester; 2012. [cited 2021 Apr 14]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-effect-of-cold-rolling-on-the-susceptibility-of-austenitic-stainless-steel-to-stress-corrosion-cracking-in-primary-circuit-pressurised-water-reactor-environment(43d9ea3e-e941-4412-90f6-907f715b78c5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566548.

Council of Science Editors:

Wright DM. The effect of cold rolling on the susceptibility of austenitic stainless steel to stress corrosion cracking in primary circuit pressurised water reactor environment. [Doctoral Dissertation]. University of Manchester; 2012. Available from: https://www.research.manchester.ac.uk/portal/en/theses/the-effect-of-cold-rolling-on-the-susceptibility-of-austenitic-stainless-steel-to-stress-corrosion-cracking-in-primary-circuit-pressurised-water-reactor-environment(43d9ea3e-e941-4412-90f6-907f715b78c5).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.566548


University of Manchester

21. Necib Ammour, Ouarda. Effect of platinum group metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors.

Degree: PhD, 2010, University of Manchester

 In pressurised water reactors (PWRs), hydrogen overpressure is used to keep the corrosion potential below the threshold for onset of intergranular stress corrosion cracking (IGSCC)… (more)

Subjects/Keywords: 621.48; SCC; PGMs; 304SS; PWR

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APA (6th Edition):

Necib Ammour, O. (2010). Effect of platinum group metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors. (Doctoral Dissertation). University of Manchester. Retrieved from https://www.research.manchester.ac.uk/portal/en/theses/effect-of-platinum-group-metal-pgm-additions-on-the-stress-corrosion-cracking-resistance-of-type-304-stainless-steel-in-pressurised-water-reactors(d7578933-6268-4fe8-819e-7b9b066f5c2e).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.518810

Chicago Manual of Style (16th Edition):

Necib Ammour, Ouarda. “Effect of platinum group metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors.” 2010. Doctoral Dissertation, University of Manchester. Accessed April 14, 2021. https://www.research.manchester.ac.uk/portal/en/theses/effect-of-platinum-group-metal-pgm-additions-on-the-stress-corrosion-cracking-resistance-of-type-304-stainless-steel-in-pressurised-water-reactors(d7578933-6268-4fe8-819e-7b9b066f5c2e).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.518810.

MLA Handbook (7th Edition):

Necib Ammour, Ouarda. “Effect of platinum group metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors.” 2010. Web. 14 Apr 2021.

Vancouver:

Necib Ammour O. Effect of platinum group metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors. [Internet] [Doctoral dissertation]. University of Manchester; 2010. [cited 2021 Apr 14]. Available from: https://www.research.manchester.ac.uk/portal/en/theses/effect-of-platinum-group-metal-pgm-additions-on-the-stress-corrosion-cracking-resistance-of-type-304-stainless-steel-in-pressurised-water-reactors(d7578933-6268-4fe8-819e-7b9b066f5c2e).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.518810.

Council of Science Editors:

Necib Ammour O. Effect of platinum group metal (PGM) additions on the stress corrosion cracking resistance of type 304 stainless steel in pressurised water reactors. [Doctoral Dissertation]. University of Manchester; 2010. Available from: https://www.research.manchester.ac.uk/portal/en/theses/effect-of-platinum-group-metal-pgm-additions-on-the-stress-corrosion-cracking-resistance-of-type-304-stainless-steel-in-pressurised-water-reactors(d7578933-6268-4fe8-819e-7b9b066f5c2e).html ; http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.518810


Université de Grenoble

22. Soulas, Romain. Effet de la cristallographie sur les premiers stades de l'oxydation des aciers austénitiques 316 L : Crystallographic effects on the early stages of 316L austenitic stainless steel oxidation.

Degree: Docteur es, Génie civil, 2012, Université de Grenoble

Les conduites primaires des centrales nucléaires REP (304L et 316L) sont protégées contre la corrosion par une couche d'oxyde. Ces conduites, qui forment une barrière… (more)

Subjects/Keywords: Oxydation; Milieu REP; 316L; MET; Oxidation; PWR environment; 316L; TEM

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APA (6th Edition):

Soulas, R. (2012). Effet de la cristallographie sur les premiers stades de l'oxydation des aciers austénitiques 316 L : Crystallographic effects on the early stages of 316L austenitic stainless steel oxidation. (Doctoral Dissertation). Université de Grenoble. Retrieved from http://www.theses.fr/2012GRENI091

Chicago Manual of Style (16th Edition):

Soulas, Romain. “Effet de la cristallographie sur les premiers stades de l'oxydation des aciers austénitiques 316 L : Crystallographic effects on the early stages of 316L austenitic stainless steel oxidation.” 2012. Doctoral Dissertation, Université de Grenoble. Accessed April 14, 2021. http://www.theses.fr/2012GRENI091.

MLA Handbook (7th Edition):

Soulas, Romain. “Effet de la cristallographie sur les premiers stades de l'oxydation des aciers austénitiques 316 L : Crystallographic effects on the early stages of 316L austenitic stainless steel oxidation.” 2012. Web. 14 Apr 2021.

Vancouver:

Soulas R. Effet de la cristallographie sur les premiers stades de l'oxydation des aciers austénitiques 316 L : Crystallographic effects on the early stages of 316L austenitic stainless steel oxidation. [Internet] [Doctoral dissertation]. Université de Grenoble; 2012. [cited 2021 Apr 14]. Available from: http://www.theses.fr/2012GRENI091.

Council of Science Editors:

Soulas R. Effet de la cristallographie sur les premiers stades de l'oxydation des aciers austénitiques 316 L : Crystallographic effects on the early stages of 316L austenitic stainless steel oxidation. [Doctoral Dissertation]. Université de Grenoble; 2012. Available from: http://www.theses.fr/2012GRENI091


University of Tennessee – Knoxville

23. Lange, Travis Louis. Methodology for an Advanced Risk Assessment of Crud Induced Power Shift using Coupled Multi-Physics Simulations and a Monte Carlo Scenario Analysis of the Potential Financial Benefits.

Degree: 2017, University of Tennessee – Knoxville

 Beginning in the 1970's, power uprates in nuclear power plants began to cause an operational problem called Crud Induced Power Shift (CIPS). Over decades, a… (more)

Subjects/Keywords: CIPS; Advanced Modeling and Simulation; CASL; Nuclear Reactors; PWR; Nuclear Engineering

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APA (6th Edition):

Lange, T. L. (2017). Methodology for an Advanced Risk Assessment of Crud Induced Power Shift using Coupled Multi-Physics Simulations and a Monte Carlo Scenario Analysis of the Potential Financial Benefits. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/4746

Chicago Manual of Style (16th Edition):

Lange, Travis Louis. “Methodology for an Advanced Risk Assessment of Crud Induced Power Shift using Coupled Multi-Physics Simulations and a Monte Carlo Scenario Analysis of the Potential Financial Benefits.” 2017. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed April 14, 2021. https://trace.tennessee.edu/utk_graddiss/4746.

MLA Handbook (7th Edition):

Lange, Travis Louis. “Methodology for an Advanced Risk Assessment of Crud Induced Power Shift using Coupled Multi-Physics Simulations and a Monte Carlo Scenario Analysis of the Potential Financial Benefits.” 2017. Web. 14 Apr 2021.

Vancouver:

Lange TL. Methodology for an Advanced Risk Assessment of Crud Induced Power Shift using Coupled Multi-Physics Simulations and a Monte Carlo Scenario Analysis of the Potential Financial Benefits. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2017. [cited 2021 Apr 14]. Available from: https://trace.tennessee.edu/utk_graddiss/4746.

Council of Science Editors:

Lange TL. Methodology for an Advanced Risk Assessment of Crud Induced Power Shift using Coupled Multi-Physics Simulations and a Monte Carlo Scenario Analysis of the Potential Financial Benefits. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2017. Available from: https://trace.tennessee.edu/utk_graddiss/4746


University of South Carolina

24. Carrilho, Leo Alves. Experimental and Computational Study of Roughened Surface For PWR Rod Bundles.

Degree: PhD, Mechanical Engineering, 2012, University of South Carolina

  PWRs fuel assemblies utilize spacer grids with flow mixing vanes to augment the coolant turbulence and improve heat transfer from the fuel rods. However,… (more)

Subjects/Keywords: Engineering; Mechanical Engineering; Fuel; Heat; PWR; Roughness; Transfer

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

APA (6th Edition):

Carrilho, L. A. (2012). Experimental and Computational Study of Roughened Surface For PWR Rod Bundles. (Doctoral Dissertation). University of South Carolina. Retrieved from https://scholarcommons.sc.edu/etd/2223

Chicago Manual of Style (16th Edition):

Carrilho, Leo Alves. “Experimental and Computational Study of Roughened Surface For PWR Rod Bundles.” 2012. Doctoral Dissertation, University of South Carolina. Accessed April 14, 2021. https://scholarcommons.sc.edu/etd/2223.

MLA Handbook (7th Edition):

Carrilho, Leo Alves. “Experimental and Computational Study of Roughened Surface For PWR Rod Bundles.” 2012. Web. 14 Apr 2021.

Vancouver:

Carrilho LA. Experimental and Computational Study of Roughened Surface For PWR Rod Bundles. [Internet] [Doctoral dissertation]. University of South Carolina; 2012. [cited 2021 Apr 14]. Available from: https://scholarcommons.sc.edu/etd/2223.

Council of Science Editors:

Carrilho LA. Experimental and Computational Study of Roughened Surface For PWR Rod Bundles. [Doctoral Dissertation]. University of South Carolina; 2012. Available from: https://scholarcommons.sc.edu/etd/2223


Utah State University

25. Blakely, Cole David. Uncertainty Quantification and Sensitivity Analysis of Multiphysics Environments for Application in Pressurized Water Reactor Design.

Degree: PhD, Mechanical and Aerospace Engineering, 2018, Utah State University

  The most common design among U.S. nuclear power plants is the pressurized water reactor (PWR). The three primary design disciplines of these plants are… (more)

Subjects/Keywords: Uncertainty Quantification; Sensitivity Analysis; Multiphysics; PWR; Mechanical Engineering

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APA (6th Edition):

Blakely, C. D. (2018). Uncertainty Quantification and Sensitivity Analysis of Multiphysics Environments for Application in Pressurized Water Reactor Design. (Doctoral Dissertation). Utah State University. Retrieved from https://digitalcommons.usu.edu/etd/7256

Chicago Manual of Style (16th Edition):

Blakely, Cole David. “Uncertainty Quantification and Sensitivity Analysis of Multiphysics Environments for Application in Pressurized Water Reactor Design.” 2018. Doctoral Dissertation, Utah State University. Accessed April 14, 2021. https://digitalcommons.usu.edu/etd/7256.

MLA Handbook (7th Edition):

Blakely, Cole David. “Uncertainty Quantification and Sensitivity Analysis of Multiphysics Environments for Application in Pressurized Water Reactor Design.” 2018. Web. 14 Apr 2021.

Vancouver:

Blakely CD. Uncertainty Quantification and Sensitivity Analysis of Multiphysics Environments for Application in Pressurized Water Reactor Design. [Internet] [Doctoral dissertation]. Utah State University; 2018. [cited 2021 Apr 14]. Available from: https://digitalcommons.usu.edu/etd/7256.

Council of Science Editors:

Blakely CD. Uncertainty Quantification and Sensitivity Analysis of Multiphysics Environments for Application in Pressurized Water Reactor Design. [Doctoral Dissertation]. Utah State University; 2018. Available from: https://digitalcommons.usu.edu/etd/7256

26. KAKUBO, MASAO. Analise sismica do predio do reator de uma central nuclear de potencia tipo PWR.

Degree: 1983, Brazil

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Dissertacao (Mestrado)

IPEN/D

Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Advisors/Committee Members: Roberto Yoshiyuti Hukai.

Subjects/Keywords: pwr type reactors; earthquakes; foundations

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APA (6th Edition):

KAKUBO, M. (1983). Analise sismica do predio do reator de uma central nuclear de potencia tipo PWR. (Masters Thesis). Brazil. Retrieved from http://repositorio.ipen.br:8080/xmlui/handle/123456789/9840

Chicago Manual of Style (16th Edition):

KAKUBO, MASAO. “Analise sismica do predio do reator de uma central nuclear de potencia tipo PWR.” 1983. Masters Thesis, Brazil. Accessed April 14, 2021. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9840.

MLA Handbook (7th Edition):

KAKUBO, MASAO. “Analise sismica do predio do reator de uma central nuclear de potencia tipo PWR.” 1983. Web. 14 Apr 2021.

Vancouver:

KAKUBO M. Analise sismica do predio do reator de uma central nuclear de potencia tipo PWR. [Internet] [Masters thesis]. Brazil; 1983. [cited 2021 Apr 14]. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/9840.

Council of Science Editors:

KAKUBO M. Analise sismica do predio do reator de uma central nuclear de potencia tipo PWR. [Masters Thesis]. Brazil; 1983. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/9840

27. TRINDADE, CARLOS E. Determinacao das propriedades modais de elementos combustiveis utilizados em reatores do tipo PWR.

Degree: 1992, Brazil

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Dissertacao (Mestrado)

IPEN/D

Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Advisors/Committee Members: Antonio Teixeira e Silva.

Subjects/Keywords: pwr type reactors; fuel elements

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APA (6th Edition):

TRINDADE, C. E. (1992). Determinacao das propriedades modais de elementos combustiveis utilizados em reatores do tipo PWR. (Masters Thesis). Brazil. Retrieved from http://repositorio.ipen.br:8080/xmlui/handle/123456789/10299

Chicago Manual of Style (16th Edition):

TRINDADE, CARLOS E. “Determinacao das propriedades modais de elementos combustiveis utilizados em reatores do tipo PWR.” 1992. Masters Thesis, Brazil. Accessed April 14, 2021. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10299.

MLA Handbook (7th Edition):

TRINDADE, CARLOS E. “Determinacao das propriedades modais de elementos combustiveis utilizados em reatores do tipo PWR.” 1992. Web. 14 Apr 2021.

Vancouver:

TRINDADE CE. Determinacao das propriedades modais de elementos combustiveis utilizados em reatores do tipo PWR. [Internet] [Masters thesis]. Brazil; 1992. [cited 2021 Apr 14]. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/10299.

Council of Science Editors:

TRINDADE CE. Determinacao das propriedades modais de elementos combustiveis utilizados em reatores do tipo PWR. [Masters Thesis]. Brazil; 1992. Available from: http://repositorio.ipen.br:8080/xmlui/handle/123456789/10299


Université de Bordeaux I

28. Ta, Ha Phuong. Etude de la relation structure - toxicité des protéines amyloïdes en interaction avec des membranes modèles : Synthesis, structural analysis, and assembly of water soluble quinoline-based oligoamide foldamers.

Degree: Docteur es, Chimie-physique, 2011, Université de Bordeaux I

Ce mémoire rapporte les études de protéines amyloïdes en interaction avec des membranes modèle afin d’établir une relation structure toxicité. Nous avons choisi différents modèles… (more)

Subjects/Keywords: Amyloïde; Prion; HET-s (218-289); Ellipsométrie; Tensiométrie; PM-IRRAS; ATR-FTIR; PWR; Amyloid; Prion; HET-s (218-289); Ellipsometry; Tensiometry; PM-IRRAS; ATR-FTIR; PWR

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APA (6th Edition):

Ta, H. P. (2011). Etude de la relation structure - toxicité des protéines amyloïdes en interaction avec des membranes modèles : Synthesis, structural analysis, and assembly of water soluble quinoline-based oligoamide foldamers. (Doctoral Dissertation). Université de Bordeaux I. Retrieved from http://www.theses.fr/2011BOR14361

Chicago Manual of Style (16th Edition):

Ta, Ha Phuong. “Etude de la relation structure - toxicité des protéines amyloïdes en interaction avec des membranes modèles : Synthesis, structural analysis, and assembly of water soluble quinoline-based oligoamide foldamers.” 2011. Doctoral Dissertation, Université de Bordeaux I. Accessed April 14, 2021. http://www.theses.fr/2011BOR14361.

MLA Handbook (7th Edition):

Ta, Ha Phuong. “Etude de la relation structure - toxicité des protéines amyloïdes en interaction avec des membranes modèles : Synthesis, structural analysis, and assembly of water soluble quinoline-based oligoamide foldamers.” 2011. Web. 14 Apr 2021.

Vancouver:

Ta HP. Etude de la relation structure - toxicité des protéines amyloïdes en interaction avec des membranes modèles : Synthesis, structural analysis, and assembly of water soluble quinoline-based oligoamide foldamers. [Internet] [Doctoral dissertation]. Université de Bordeaux I; 2011. [cited 2021 Apr 14]. Available from: http://www.theses.fr/2011BOR14361.

Council of Science Editors:

Ta HP. Etude de la relation structure - toxicité des protéines amyloïdes en interaction avec des membranes modèles : Synthesis, structural analysis, and assembly of water soluble quinoline-based oligoamide foldamers. [Doctoral Dissertation]. Université de Bordeaux I; 2011. Available from: http://www.theses.fr/2011BOR14361


Brno University of Technology

29. Konopová, Tamara. Jaderné palivo v provozních podmínkách: Nuclear Fuel in Operational Conditions.

Degree: 2019, Brno University of Technology

 This thesis deals with the issue of nuclear fuel. Firstly, the problem of nuclear fuel in the implementation for pressurized water reactors is presented. Production… (more)

Subjects/Keywords: PWR; VVER; jaderné palivo; výroba jaderného paliva; jevy v palivu; vyhořívající absorbátory; gadolinium; erbium; PWR; VVER; nuclear fuel; nuclear fuel cycle; phenomena of fuel burnup; burnable absorber; gadolinium; erbium

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

APA (6th Edition):

Konopová, T. (2019). Jaderné palivo v provozních podmínkách: Nuclear Fuel in Operational Conditions. (Thesis). Brno University of Technology. Retrieved from http://hdl.handle.net/11012/60503

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):

Konopová, Tamara. “Jaderné palivo v provozních podmínkách: Nuclear Fuel in Operational Conditions.” 2019. Thesis, Brno University of Technology. Accessed April 14, 2021. http://hdl.handle.net/11012/60503.

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

MLA Handbook (7th Edition):

Konopová, Tamara. “Jaderné palivo v provozních podmínkách: Nuclear Fuel in Operational Conditions.” 2019. Web. 14 Apr 2021.

Vancouver:

Konopová T. Jaderné palivo v provozních podmínkách: Nuclear Fuel in Operational Conditions. [Internet] [Thesis]. Brno University of Technology; 2019. [cited 2021 Apr 14]. Available from: http://hdl.handle.net/11012/60503.

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

Council of Science Editors:

Konopová T. Jaderné palivo v provozních podmínkách: Nuclear Fuel in Operational Conditions. [Thesis]. Brno University of Technology; 2019. Available from: http://hdl.handle.net/11012/60503

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

30. Rafael Radé Pacheco. Desenvolvimento de modelos analítico e numérico associados ao fenômeno de condensação por contato direto em tanque de alívio de reator PWR.

Degree: 2018, University of São Paulo

O fenômeno de injeção de vapor em tanques de alívio é de relevância no projeto de reatores de água leve, sejam eles do tipo reator… (more)

Subjects/Keywords: água; BWR; elementos finitos; injeção; modelo numérico; PWR; tanque de alívio; vapor; volumes finitos; BWR; finite elements; finite volumes; injection; numerical model; PWR; relief tank; steam; thermodynamics; turbulence; water

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

APA (6th Edition):

Pacheco, R. R. (2018). Desenvolvimento de modelos analítico e numérico associados ao fenômeno de condensação por contato direto em tanque de alívio de reator PWR. (Doctoral Dissertation). University of São Paulo. Retrieved from http://www.teses.usp.br/teses/disponiveis/85/85133/tde-23102018-160457/

Chicago Manual of Style (16th Edition):

Pacheco, Rafael Radé. “Desenvolvimento de modelos analítico e numérico associados ao fenômeno de condensação por contato direto em tanque de alívio de reator PWR.” 2018. Doctoral Dissertation, University of São Paulo. Accessed April 14, 2021. http://www.teses.usp.br/teses/disponiveis/85/85133/tde-23102018-160457/.

MLA Handbook (7th Edition):

Pacheco, Rafael Radé. “Desenvolvimento de modelos analítico e numérico associados ao fenômeno de condensação por contato direto em tanque de alívio de reator PWR.” 2018. Web. 14 Apr 2021.

Vancouver:

Pacheco RR. Desenvolvimento de modelos analítico e numérico associados ao fenômeno de condensação por contato direto em tanque de alívio de reator PWR. [Internet] [Doctoral dissertation]. University of São Paulo; 2018. [cited 2021 Apr 14]. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-23102018-160457/.

Council of Science Editors:

Pacheco RR. Desenvolvimento de modelos analítico e numérico associados ao fenômeno de condensação por contato direto em tanque de alívio de reator PWR. [Doctoral Dissertation]. University of São Paulo; 2018. Available from: http://www.teses.usp.br/teses/disponiveis/85/85133/tde-23102018-160457/

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