Advanced search options

Advanced Search Options 🞨

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

Find ETDs with:

in
/  
in
/  
in
/  
in

Written in Published in Earliest date Latest date

Sorted by

Results per page:

Sorted by: relevance · author · university · dateNew search

You searched for subject:(Boiling Water Reactor). Showing records 1 – 25 of 25 total matches.

Search Limiters

Last 2 Years | English Only

No search limiters apply to these results.

▼ Search Limiters


Penn State University

1. Magedanz, Jeffrey William. DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS.

Degree: MS, Nuclear Engineering, 2010, Penn State University

 Computer simulation of the behavior of nuclear reactors is an important part of their design, regulation, and operation. A phonomenon that is the subject of… (more)

Subjects/Keywords: boiling water reactor; stability analysis

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Magedanz, J. W. (2010). DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS. (Masters Thesis). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/10782

Chicago Manual of Style (16th Edition):

Magedanz, Jeffrey William. “DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS.” 2010. Masters Thesis, Penn State University. Accessed December 14, 2019. https://etda.libraries.psu.edu/catalog/10782.

MLA Handbook (7th Edition):

Magedanz, Jeffrey William. “DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS.” 2010. Web. 14 Dec 2019.

Vancouver:

Magedanz JW. DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS. [Internet] [Masters thesis]. Penn State University; 2010. [cited 2019 Dec 14]. Available from: https://etda.libraries.psu.edu/catalog/10782.

Council of Science Editors:

Magedanz JW. DEVELOPMENT OF MODEL OF OSKARSHAMN-2 REACTOR FOR ASSESSMENT OF TRACE/PARCS FOR BOILING WATER REACTOR STABILITY ANALYSIS. [Masters Thesis]. Penn State University; 2010. Available from: https://etda.libraries.psu.edu/catalog/10782

2. 熊谷, 康介. 沸騰水型軽水炉上部プレナムにおける音響共鳴現象の可視化(要旨).

Degree: 修士(環境学), 2017, The University of Tokyo / 東京大学

 In recent years, the power uprate of Boiling Water Reactors have been conducted at several existing power plants as a way to improve plant economy.… (more)

Subjects/Keywords: Boiling Water Reactor; Acoustic vibration; Dynamic PIV

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

熊谷, . (2017). 沸騰水型軽水炉上部プレナムにおける音響共鳴現象の可視化(要旨). (Thesis). The University of Tokyo / 東京大学. Retrieved from http://hdl.handle.net/2261/37198

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):

熊谷, 康介. “沸騰水型軽水炉上部プレナムにおける音響共鳴現象の可視化(要旨).” 2017. Thesis, The University of Tokyo / 東京大学. Accessed December 14, 2019. http://hdl.handle.net/2261/37198.

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

MLA Handbook (7th Edition):

熊谷, 康介. “沸騰水型軽水炉上部プレナムにおける音響共鳴現象の可視化(要旨).” 2017. Web. 14 Dec 2019.

Vancouver:

熊谷 . 沸騰水型軽水炉上部プレナムにおける音響共鳴現象の可視化(要旨). [Internet] [Thesis]. The University of Tokyo / 東京大学; 2017. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/2261/37198.

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

Council of Science Editors:

熊谷 . 沸騰水型軽水炉上部プレナムにおける音響共鳴現象の可視化(要旨). [Thesis]. The University of Tokyo / 東京大学; 2017. Available from: http://hdl.handle.net/2261/37198

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


University of Tennessee – Knoxville

3. Galloway, Jack Douglas. Boiling Water Reactor Core Simulation with Generalized Isotopic Inventory Tracking for Actinide Management.

Degree: 2010, University of Tennessee – Knoxville

 The computational ability to accurately simulate boiling water reactor operation under the full range of standard steady-state operation, along with the capability to fully track… (more)

Subjects/Keywords: NESTLE; ORIGEN; boiling water reactor; drift-flux; Nuclear Engineering

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Galloway, J. D. (2010). Boiling Water Reactor Core Simulation with Generalized Isotopic Inventory Tracking for Actinide Management. (Doctoral Dissertation). University of Tennessee – Knoxville. Retrieved from https://trace.tennessee.edu/utk_graddiss/798

Chicago Manual of Style (16th Edition):

Galloway, Jack Douglas. “Boiling Water Reactor Core Simulation with Generalized Isotopic Inventory Tracking for Actinide Management.” 2010. Doctoral Dissertation, University of Tennessee – Knoxville. Accessed December 14, 2019. https://trace.tennessee.edu/utk_graddiss/798.

MLA Handbook (7th Edition):

Galloway, Jack Douglas. “Boiling Water Reactor Core Simulation with Generalized Isotopic Inventory Tracking for Actinide Management.” 2010. Web. 14 Dec 2019.

Vancouver:

Galloway JD. Boiling Water Reactor Core Simulation with Generalized Isotopic Inventory Tracking for Actinide Management. [Internet] [Doctoral dissertation]. University of Tennessee – Knoxville; 2010. [cited 2019 Dec 14]. Available from: https://trace.tennessee.edu/utk_graddiss/798.

Council of Science Editors:

Galloway JD. Boiling Water Reactor Core Simulation with Generalized Isotopic Inventory Tracking for Actinide Management. [Doctoral Dissertation]. University of Tennessee – Knoxville; 2010. Available from: https://trace.tennessee.edu/utk_graddiss/798


Delft University of Technology

4. Zboray, R. An experimental and modelling study of natural-circulation boiling water reactor dynamics.

Degree: 2002, Delft University of Technology

Subjects/Keywords: Boiling water reactor; natural circulation; dynamics

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Zboray, R. (2002). An experimental and modelling study of natural-circulation boiling water reactor dynamics. (Doctoral Dissertation). Delft University of Technology. Retrieved from http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce

Chicago Manual of Style (16th Edition):

Zboray, R. “An experimental and modelling study of natural-circulation boiling water reactor dynamics.” 2002. Doctoral Dissertation, Delft University of Technology. Accessed December 14, 2019. http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce.

MLA Handbook (7th Edition):

Zboray, R. “An experimental and modelling study of natural-circulation boiling water reactor dynamics.” 2002. Web. 14 Dec 2019.

Vancouver:

Zboray R. An experimental and modelling study of natural-circulation boiling water reactor dynamics. [Internet] [Doctoral dissertation]. Delft University of Technology; 2002. [cited 2019 Dec 14]. Available from: http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce.

Council of Science Editors:

Zboray R. An experimental and modelling study of natural-circulation boiling water reactor dynamics. [Doctoral Dissertation]. Delft University of Technology; 2002. Available from: http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; urn:NBN:nl:ui:24-uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce ; http://resolver.tudelft.nl/uuid:08f07c23-403b-46ee-9262-7b91b20ac6ce


Purdue University

5. Cheng, Ling. Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor.

Degree: PhD, Nuclear Engineering, 2015, Purdue University

 The thesis evaluates the safety systems in the next generation boiling water reactor by analyzing the main steam line break loss of coolant accident performed… (more)

Subjects/Keywords: main steam line break analysis; next generation boiling water reactor; numerical simulation; one dimensional integral model; safety systems; suppression pool mixing

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Cheng, L. (2015). Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor. (Doctoral Dissertation). Purdue University. Retrieved from https://docs.lib.purdue.edu/open_access_dissertations/1176

Chicago Manual of Style (16th Edition):

Cheng, Ling. “Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor.” 2015. Doctoral Dissertation, Purdue University. Accessed December 14, 2019. https://docs.lib.purdue.edu/open_access_dissertations/1176.

MLA Handbook (7th Edition):

Cheng, Ling. “Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor.” 2015. Web. 14 Dec 2019.

Vancouver:

Cheng L. Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor. [Internet] [Doctoral dissertation]. Purdue University; 2015. [cited 2019 Dec 14]. Available from: https://docs.lib.purdue.edu/open_access_dissertations/1176.

Council of Science Editors:

Cheng L. Evaluation of the Safety Systems in the Next Generation Boiling Water Reactor. [Doctoral Dissertation]. Purdue University; 2015. Available from: https://docs.lib.purdue.edu/open_access_dissertations/1176


Texas A&M University

6. Solom, Matthew Alan. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.

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

 In current Station Blackout analyses for Generation II Light Water Reactors, battery failure in 4-8 hours is expected to result in the failure of the… (more)

Subjects/Keywords: thermal stratification; chugging; Direct Contact Condensation (DCC); Reactor Core Isolation Cooling (RCIC) System; Boiling Water Reactor (BWR); suppression pool; Station Blackout (SBO)

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Solom, M. A. (2016). Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. (Doctoral Dissertation). Texas A&M University. Retrieved from http://hdl.handle.net/1969.1/157135

Chicago Manual of Style (16th Edition):

Solom, Matthew Alan. “Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.” 2016. Doctoral Dissertation, Texas A&M University. Accessed December 14, 2019. http://hdl.handle.net/1969.1/157135.

MLA Handbook (7th Edition):

Solom, Matthew Alan. “Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation.” 2016. Web. 14 Dec 2019.

Vancouver:

Solom MA. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. [Internet] [Doctoral dissertation]. Texas A&M University; 2016. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/1969.1/157135.

Council of Science Editors:

Solom MA. Experimental Study on Suppression Chamber Thermal-Hydraulic Behavior for Long-Term Reactor Core Isolation Cooling System Operation. [Doctoral Dissertation]. Texas A&M University; 2016. Available from: http://hdl.handle.net/1969.1/157135

7. Tuvesson, Anton. Förhindra härdsmältningsförlopp : Vatteninmatningsflöde som hindrar tankgenomsmältning.

Degree: 2019, , Department of Mechanical Engineering

Examensarbetet behandlar problematik som uppstår vid härdsmältningsförlopp i en kärnkraftsreaktor av typen kokvattensreaktor. Resultatet ska användas som riktlinjer till strategier som utvecklas av Severe… (more)

Subjects/Keywords: Boiling water reactor; Core cooling; Core meltdown; Water input; Zirconium oxidation; Kokvattensreaktor (BWR); Härdkylning; Vatteninmatning; Tankgenomsmältning; Zirkonium-oxidation; Energy Engineering; Energiteknik; Other Mechanical Engineering; Annan maskinteknik

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Tuvesson, A. (2019). Förhindra härdsmältningsförlopp : Vatteninmatningsflöde som hindrar tankgenomsmältning. (Thesis). , Department of Mechanical Engineering. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:bth-18537

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):

Tuvesson, Anton. “Förhindra härdsmältningsförlopp : Vatteninmatningsflöde som hindrar tankgenomsmältning.” 2019. Thesis, , Department of Mechanical Engineering. Accessed December 14, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:bth-18537.

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

MLA Handbook (7th Edition):

Tuvesson, Anton. “Förhindra härdsmältningsförlopp : Vatteninmatningsflöde som hindrar tankgenomsmältning.” 2019. Web. 14 Dec 2019.

Vancouver:

Tuvesson A. Förhindra härdsmältningsförlopp : Vatteninmatningsflöde som hindrar tankgenomsmältning. [Internet] [Thesis]. , Department of Mechanical Engineering; 2019. [cited 2019 Dec 14]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:bth-18537.

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

Council of Science Editors:

Tuvesson A. Förhindra härdsmältningsförlopp : Vatteninmatningsflöde som hindrar tankgenomsmältning. [Thesis]. , Department of Mechanical Engineering; 2019. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:bth-18537

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

8. Toivonen, Aki. Stress Corrosion Crack Growth Rate Measurement in High Temperature Water Using Small Precracked Bend Specimens.

Degree: 2004, VTT Technical Research Centre of Finland

 The applicability of elastic-plastic fracture mechanics to stress corrosion crack growth rate measurements was studied. Several test series were performed on small elastic-plastically loaded SEN(B)… (more)

Subjects/Keywords: stress corrosion cracking; stress corrosion testing; linear-elastic fracture mechanics; elastic-plastic fracture mechanics; boiling water reactor; stainless steel; nickel-base weld metal; crack growth rate; fracture surface morphology

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Toivonen, A. (2004). Stress Corrosion Crack Growth Rate Measurement in High Temperature Water Using Small Precracked Bend Specimens. (Thesis). VTT Technical Research Centre of Finland. Retrieved from http://lib.tkk.fi/Diss/2004/isbn9513863832/

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):

Toivonen, Aki. “Stress Corrosion Crack Growth Rate Measurement in High Temperature Water Using Small Precracked Bend Specimens.” 2004. Thesis, VTT Technical Research Centre of Finland. Accessed December 14, 2019. http://lib.tkk.fi/Diss/2004/isbn9513863832/.

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

MLA Handbook (7th Edition):

Toivonen, Aki. “Stress Corrosion Crack Growth Rate Measurement in High Temperature Water Using Small Precracked Bend Specimens.” 2004. Web. 14 Dec 2019.

Vancouver:

Toivonen A. Stress Corrosion Crack Growth Rate Measurement in High Temperature Water Using Small Precracked Bend Specimens. [Internet] [Thesis]. VTT Technical Research Centre of Finland; 2004. [cited 2019 Dec 14]. Available from: http://lib.tkk.fi/Diss/2004/isbn9513863832/.

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

Council of Science Editors:

Toivonen A. Stress Corrosion Crack Growth Rate Measurement in High Temperature Water Using Small Precracked Bend Specimens. [Thesis]. VTT Technical Research Centre of Finland; 2004. Available from: http://lib.tkk.fi/Diss/2004/isbn9513863832/

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

9. Ohlsson, Daniel. Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2.

Degree: IT and Land Management, 2017, University of Gävle

  In the process of a boiling water reactor, high-levels of waste and radiation occur, where almost all the dose per person of the radiation… (more)

Subjects/Keywords: Boiling Water Reactor; BWR; Stellite; Forsmark; Cobalt; Cobalt-59; Kokvattenreaktor; BWR; Stellite; Forsmark; kobolt; kobolt-59; kobolt-60; korrosion; dosrat; strålning; Other Mechanical Engineering; Annan maskinteknik

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Ohlsson, D. (2017). Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2. (Thesis). University of Gävle. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130

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):

Ohlsson, Daniel. “Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2.” 2017. Thesis, University of Gävle. Accessed December 14, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130.

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

MLA Handbook (7th Edition):

Ohlsson, Daniel. “Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2.” 2017. Web. 14 Dec 2019.

Vancouver:

Ohlsson D. Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2. [Internet] [Thesis]. University of Gävle; 2017. [cited 2019 Dec 14]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130.

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

Council of Science Editors:

Ohlsson D. Kartläggning av ventiler innehållande Stellite i reaktornära vattensystem på Forsmark 2. [Thesis]. University of Gävle; 2017. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:hig:diva-25130

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

10. Ferrer, Alexandre. Modélisation des mécanismes de formation sous ébullition locale des dépôts sur les gaines de combustible des réacteurs à eau sous pression conduisant à des activités volumiques importantes : Modelling of crud growth mechanisms under local boiling conditions in pressurized water reactors fuel clads leading to important volumes activities.

Degree: Docteur es, Physique des particules élémentaires, 2013, Université de Strasbourg

Les composants du circuit primaire des réacteurs nucléaires à eau sous pression (REP) subissent une corrosion généralisée entraînant le relâchement d'espèces solubles dans le fluide… (more)

Subjects/Keywords: Réacteur à eau pressurisée; Activités volumiques; Contamination; Produits de corrosion; Ebullition; Dépôt; Thermohydraulique; Pressurized water reactor; Volume activities; Contamination; Corrosion products; Boiling; Deposit; Thermal-hydraulic; 539.7

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Ferrer, A. (2013). Modélisation des mécanismes de formation sous ébullition locale des dépôts sur les gaines de combustible des réacteurs à eau sous pression conduisant à des activités volumiques importantes : Modelling of crud growth mechanisms under local boiling conditions in pressurized water reactors fuel clads leading to important volumes activities. (Doctoral Dissertation). Université de Strasbourg. Retrieved from http://www.theses.fr/2013STRAE040

Chicago Manual of Style (16th Edition):

Ferrer, Alexandre. “Modélisation des mécanismes de formation sous ébullition locale des dépôts sur les gaines de combustible des réacteurs à eau sous pression conduisant à des activités volumiques importantes : Modelling of crud growth mechanisms under local boiling conditions in pressurized water reactors fuel clads leading to important volumes activities.” 2013. Doctoral Dissertation, Université de Strasbourg. Accessed December 14, 2019. http://www.theses.fr/2013STRAE040.

MLA Handbook (7th Edition):

Ferrer, Alexandre. “Modélisation des mécanismes de formation sous ébullition locale des dépôts sur les gaines de combustible des réacteurs à eau sous pression conduisant à des activités volumiques importantes : Modelling of crud growth mechanisms under local boiling conditions in pressurized water reactors fuel clads leading to important volumes activities.” 2013. Web. 14 Dec 2019.

Vancouver:

Ferrer A. Modélisation des mécanismes de formation sous ébullition locale des dépôts sur les gaines de combustible des réacteurs à eau sous pression conduisant à des activités volumiques importantes : Modelling of crud growth mechanisms under local boiling conditions in pressurized water reactors fuel clads leading to important volumes activities. [Internet] [Doctoral dissertation]. Université de Strasbourg; 2013. [cited 2019 Dec 14]. Available from: http://www.theses.fr/2013STRAE040.

Council of Science Editors:

Ferrer A. Modélisation des mécanismes de formation sous ébullition locale des dépôts sur les gaines de combustible des réacteurs à eau sous pression conduisant à des activités volumiques importantes : Modelling of crud growth mechanisms under local boiling conditions in pressurized water reactors fuel clads leading to important volumes activities. [Doctoral Dissertation]. Université de Strasbourg; 2013. Available from: http://www.theses.fr/2013STRAE040


Université de Grenoble

11. Gueguen, Jil. Contribution à la modélisation multidimensionnelle des écoulements bouillants convectifs en conduite haute pression pour l'application au cas des réacteurs à eau pressurisée : Contribution to the modelling of multidimentional high pressure boiling flows relative to pwr’s thermal-hydraulic conditions.

Degree: Docteur es, Mécanique des fluides, procédés, énergétique, 2013, Université de Grenoble

Cette étude concerne la caractérisation des écoulements diphasiques bouillants convectifs à haute pression rencontrés dans les réacteurs à eau sous pression (REP). La simulation de… (more)

Subjects/Keywords: Thermohydraulique; Écoulements diphasiques; Modélisation; Turbulence; Réacteur à eau pressurisée; Crise d'ébullition; Thermohydraulics; Two-phase flows; Modelling; Turbulence; Pressurized water reactor; Boiling crisis; 620

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Gueguen, J. (2013). Contribution à la modélisation multidimensionnelle des écoulements bouillants convectifs en conduite haute pression pour l'application au cas des réacteurs à eau pressurisée : Contribution to the modelling of multidimentional high pressure boiling flows relative to pwr’s thermal-hydraulic conditions. (Doctoral Dissertation). Université de Grenoble. Retrieved from http://www.theses.fr/2013GRENI055

Chicago Manual of Style (16th Edition):

Gueguen, Jil. “Contribution à la modélisation multidimensionnelle des écoulements bouillants convectifs en conduite haute pression pour l'application au cas des réacteurs à eau pressurisée : Contribution to the modelling of multidimentional high pressure boiling flows relative to pwr’s thermal-hydraulic conditions.” 2013. Doctoral Dissertation, Université de Grenoble. Accessed December 14, 2019. http://www.theses.fr/2013GRENI055.

MLA Handbook (7th Edition):

Gueguen, Jil. “Contribution à la modélisation multidimensionnelle des écoulements bouillants convectifs en conduite haute pression pour l'application au cas des réacteurs à eau pressurisée : Contribution to the modelling of multidimentional high pressure boiling flows relative to pwr’s thermal-hydraulic conditions.” 2013. Web. 14 Dec 2019.

Vancouver:

Gueguen J. Contribution à la modélisation multidimensionnelle des écoulements bouillants convectifs en conduite haute pression pour l'application au cas des réacteurs à eau pressurisée : Contribution to the modelling of multidimentional high pressure boiling flows relative to pwr’s thermal-hydraulic conditions. [Internet] [Doctoral dissertation]. Université de Grenoble; 2013. [cited 2019 Dec 14]. Available from: http://www.theses.fr/2013GRENI055.

Council of Science Editors:

Gueguen J. Contribution à la modélisation multidimensionnelle des écoulements bouillants convectifs en conduite haute pression pour l'application au cas des réacteurs à eau pressurisée : Contribution to the modelling of multidimentional high pressure boiling flows relative to pwr’s thermal-hydraulic conditions. [Doctoral Dissertation]. Université de Grenoble; 2013. Available from: http://www.theses.fr/2013GRENI055


Penn State University

12. Kim, Han Sang. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS.

Degree: PhD, Nuclear Engineering, 2007, Penn State University

 Existing computer codes, developed by Macdonald et al. for modeling water chemistry and estimating the accumulated damage from the stress corrosion cracking in the operating… (more)

Subjects/Keywords: Impedance measurement; Polarization curve; Corrosion potential; Boiling water reactor; Pressurized water reactor; Point defect model

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Kim, H. S. (2007). A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS. (Doctoral Dissertation). Penn State University. Retrieved from https://etda.libraries.psu.edu/catalog/8076

Chicago Manual of Style (16th Edition):

Kim, Han Sang. “A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS.” 2007. Doctoral Dissertation, Penn State University. Accessed December 14, 2019. https://etda.libraries.psu.edu/catalog/8076.

MLA Handbook (7th Edition):

Kim, Han Sang. “A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS.” 2007. Web. 14 Dec 2019.

Vancouver:

Kim HS. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS. [Internet] [Doctoral dissertation]. Penn State University; 2007. [cited 2019 Dec 14]. Available from: https://etda.libraries.psu.edu/catalog/8076.

Council of Science Editors:

Kim HS. A STUDY FOR MODELING ELECTROCHEMISTRY IN LIGHT WATER REACTORS. [Doctoral Dissertation]. Penn State University; 2007. Available from: https://etda.libraries.psu.edu/catalog/8076


EPFL

13. Giust, Flavio Dante. Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies.

Degree: 2012, EPFL

 The present doctoral research aims at the appraisal of nodal core simulators used for the calculation of commercial boiling water reactor (BWR) cores, against measurements… (more)

Subjects/Keywords: nodal methods; pin-power reconstruction; core heterogeneities; boiling water reactor (BWR); zero-power research reactor; experimental validation; total-fission rate; neutron; current; three-dimensional distribution; LWR-PROTEUS experimental programme; HELIOS; PRESTO-2; CASMO-5; SIMULATE-5; MCNPX

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Giust, F. D. (2012). Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies. (Thesis). EPFL. Retrieved from http://infoscience.epfl.ch/record/169997

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):

Giust, Flavio Dante. “Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies.” 2012. Thesis, EPFL. Accessed December 14, 2019. http://infoscience.epfl.ch/record/169997.

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

MLA Handbook (7th Edition):

Giust, Flavio Dante. “Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies.” 2012. Web. 14 Dec 2019.

Vancouver:

Giust FD. Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies. [Internet] [Thesis]. EPFL; 2012. [cited 2019 Dec 14]. Available from: http://infoscience.epfl.ch/record/169997.

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

Council of Science Editors:

Giust FD. Appraisal of Core Analysis Methods against Zero-Power Experiments on Full-Scale BWR Fuel Assemblies. [Thesis]. EPFL; 2012. Available from: http://infoscience.epfl.ch/record/169997

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


University of Akron

14. Niu, Wei. Corrosion Study Of Interstitially Hardened SS 316L AND IN718 In Simulated Light Water Reactor Conditions.

Degree: PhD, Chemical Engineering, 2017, University of Akron

 Corrosion of structure materials in light water reactors (LWRs) can be ultimately equally disastrous as the immediate attack and degradation of components, which arise from… (more)

Subjects/Keywords: Chemical Engineering; Materials Science; Nuclear Engineering; SS 316L; IN 718; Interstitially hardening; Boiling water reactor; normal water chemistry; hydrogen water chemistry; focused ion beam; transmission electron spectroscopy; Transgranular stress corrosion cracking

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Niu, W. (2017). Corrosion Study Of Interstitially Hardened SS 316L AND IN718 In Simulated Light Water Reactor Conditions. (Doctoral Dissertation). University of Akron. Retrieved from http://rave.ohiolink.edu/etdc/view?acc_num=akron1490998919124215

Chicago Manual of Style (16th Edition):

Niu, Wei. “Corrosion Study Of Interstitially Hardened SS 316L AND IN718 In Simulated Light Water Reactor Conditions.” 2017. Doctoral Dissertation, University of Akron. Accessed December 14, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=akron1490998919124215.

MLA Handbook (7th Edition):

Niu, Wei. “Corrosion Study Of Interstitially Hardened SS 316L AND IN718 In Simulated Light Water Reactor Conditions.” 2017. Web. 14 Dec 2019.

Vancouver:

Niu W. Corrosion Study Of Interstitially Hardened SS 316L AND IN718 In Simulated Light Water Reactor Conditions. [Internet] [Doctoral dissertation]. University of Akron; 2017. [cited 2019 Dec 14]. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=akron1490998919124215.

Council of Science Editors:

Niu W. Corrosion Study Of Interstitially Hardened SS 316L AND IN718 In Simulated Light Water Reactor Conditions. [Doctoral Dissertation]. University of Akron; 2017. Available from: http://rave.ohiolink.edu/etdc/view?acc_num=akron1490998919124215

15. Constanda, Daniel. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate.

Degree: Applied Nuclear Physics, 2015, Uppsala University

  This study aims to improve the modeling of partial SCRAM in the BISON plant model for the Forsmark 2 nuclear reactor after power uprate.… (more)

Subjects/Keywords: nuclear power; bwr; boiling water reactor; BISON; POLCA; partial SCRAM modeling; control rod effect; transients

Water Reactor A Boiling Water Reactor (BWR) is one of the two most common light… …difference is what gives them their names, the water inside the reactor of a BWR is boiling but in… …reactor and gives background to the study. It concludes with the aim of the study. 1.1 Boiling… …water reactor types, the other is Pressurized Water Reactor (PWR). The most salient… …reactor. For the test case runback is activated directly before the water level is affected by… 

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Constanda, D. (2015). Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate. (Thesis). Uppsala University. Retrieved from http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360

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):

Constanda, Daniel. “Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate.” 2015. Thesis, Uppsala University. Accessed December 14, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360.

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

MLA Handbook (7th Edition):

Constanda, Daniel. “Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate.” 2015. Web. 14 Dec 2019.

Vancouver:

Constanda D. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate. [Internet] [Thesis]. Uppsala University; 2015. [cited 2019 Dec 14]. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360.

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

Council of Science Editors:

Constanda D. Control Rod Effect at Partial SCRAM : Upgrade of Plant Model for Forsmark 2 in BISON After Power Uprate. [Thesis]. Uppsala University; 2015. Available from: http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-269360

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

16. Younkin, Timothy R. Piecewise prediction of nuclide densities with control blade use as a function of burnup in BWR used nuclear fuel.

Degree: MS, Mechanical Engineering, 2014, Georgia Tech

 In order to improve the efficiency of dry used nuclear fuel (UNF) storage, reduced reactivity methods are being developed for various reactor types and operating… (more)

Subjects/Keywords: Boiling water reactor; BWR; Used nuclear fuel; UNF; Burnup credit; Isotopics; Nuclides; Scale; Triton

…Installation DOE United States Department Of Energy BWR Boiling Water Reactor PDA method SCALE… …configurations of boiling water reactor (BWR) UNF that use reduced reactivity (burnup… …moisture separation before the steam goes to drive the main turbine. Boiling water reactor fuel… …them. The generic burnup credit cask (GBC) containing 68 boiling water reactor… …SCALE Pressurized Water Reactor Standardized Computer Analyses for Licensing Evaluation GBC… 

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Younkin, T. R. (2014). Piecewise prediction of nuclide densities with control blade use as a function of burnup in BWR used nuclear fuel. (Masters Thesis). Georgia Tech. Retrieved from http://hdl.handle.net/1853/53118

Chicago Manual of Style (16th Edition):

Younkin, Timothy R. “Piecewise prediction of nuclide densities with control blade use as a function of burnup in BWR used nuclear fuel.” 2014. Masters Thesis, Georgia Tech. Accessed December 14, 2019. http://hdl.handle.net/1853/53118.

MLA Handbook (7th Edition):

Younkin, Timothy R. “Piecewise prediction of nuclide densities with control blade use as a function of burnup in BWR used nuclear fuel.” 2014. Web. 14 Dec 2019.

Vancouver:

Younkin TR. Piecewise prediction of nuclide densities with control blade use as a function of burnup in BWR used nuclear fuel. [Internet] [Masters thesis]. Georgia Tech; 2014. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/1853/53118.

Council of Science Editors:

Younkin TR. Piecewise prediction of nuclide densities with control blade use as a function of burnup in BWR used nuclear fuel. [Masters Thesis]. Georgia Tech; 2014. Available from: http://hdl.handle.net/1853/53118

17. Mui, Travis C. TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly.

Degree: MS, Nuclear, Plasma, & Radiological Engineering, 2015, University of Illinois – Urbana-Champaign

 Best-estimate codes have been developed in the nuclear industry to design and license nuclear power plants to a greater degree of accuracy and safety assurance.… (more)

Subjects/Keywords: Thermal hydraulics; TRACE; Boiling Water Reactor (BWR); SVEA; Validation; Uncertainty quantification; Dakota; Best-estimate

…accurate best-estimate models. In a typical Boiling Water Reactor (BWR) design, several… …abnormal scenarios. To approve a nuclear reactor for operation, its design must demonstrate… …Computational simulation of a nuclear reactor and its components provides an adept method for modeling… …assess accident scenarios and reactor performance, particularly in loss-of-coolant accident… …primary goal of maintaining the reactor core in a cooled, contained state. BWR emergency core… 

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Mui, T. C. (2015). TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/89030

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):

Mui, Travis C. “TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly.” 2015. Thesis, University of Illinois – Urbana-Champaign. Accessed December 14, 2019. http://hdl.handle.net/2142/89030.

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

MLA Handbook (7th Edition):

Mui, Travis C. “TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly.” 2015. Web. 14 Dec 2019.

Vancouver:

Mui TC. TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2015. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/2142/89030.

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

Council of Science Editors:

Mui TC. TRACE code validation of boiling water reactor spray cooling injection into a SVEA fuel assembly. [Thesis]. University of Illinois – Urbana-Champaign; 2015. Available from: http://hdl.handle.net/2142/89030

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

18. Hays, Ross D. Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B.

Degree: MS, Nuclear Engineering, 2009, North Carolina State University

 A commercial nuclear power plant with a boiling water reactor will utilize between 368 and 800+ individual fuel assemblies to generate steam for 18 to… (more)

Subjects/Keywords: Boiling Water Reactor; BWR;

…limitations. As the typical Boiling Water Reactor core contains between 368 and 800 fuel assemblies… …52 1 Chapter 1 Introduction The operation of a commercial Light Water Reactor (LWR… …consideration unique to BWRs is the sequencing of the control rods. Unlike a Pressurized Water Reactor… …x29; power reactor involves the controlled conversion of energy stored in the nucleus of a… …its useful life span it is removed from the reactor and replaced with a fresh assembly. For… 

Page 1 Page 2 Page 3 Page 4 Page 5 Page 6 Page 7

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Hays, R. D. (2009). Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B. (Thesis). North Carolina State University. Retrieved from http://www.lib.ncsu.edu/resolver/1840.16/2746

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):

Hays, Ross D. “Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B.” 2009. Thesis, North Carolina State University. Accessed December 14, 2019. http://www.lib.ncsu.edu/resolver/1840.16/2746.

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

MLA Handbook (7th Edition):

Hays, Ross D. “Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B.” 2009. Web. 14 Dec 2019.

Vancouver:

Hays RD. Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B. [Internet] [Thesis]. North Carolina State University; 2009. [cited 2019 Dec 14]. Available from: http://www.lib.ncsu.edu/resolver/1840.16/2746.

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

Council of Science Editors:

Hays RD. Boiling Water Reactor In-Core Fuel Management through Parallel Simulated Annealing in FORMOSA-B. [Thesis]. North Carolina State University; 2009. Available from: http://www.lib.ncsu.edu/resolver/1840.16/2746

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

19. Furuya, M. Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs: Thermal-Hydraulic, Core-Wide, and Regional Stability Phenomena.

Degree: 2006, IOS

 Currently, 434 nuclear power plants are in operation worldwide. 21% of them are known as Boiling Water Reactors (BWRs). These BWRs have pumps that cool… (more)

Subjects/Keywords: boiling water reactor; natural circulation; regional stability; dynamics; time-series analysis; thermalhydraulic-neutrnoic coupling

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Furuya, M. (2006). Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs: Thermal-Hydraulic, Core-Wide, and Regional Stability Phenomena. (Doctoral Dissertation). IOS. Retrieved from http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120

Chicago Manual of Style (16th Edition):

Furuya, M. “Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs: Thermal-Hydraulic, Core-Wide, and Regional Stability Phenomena.” 2006. Doctoral Dissertation, IOS. Accessed December 14, 2019. http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120.

MLA Handbook (7th Edition):

Furuya, M. “Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs: Thermal-Hydraulic, Core-Wide, and Regional Stability Phenomena.” 2006. Web. 14 Dec 2019.

Vancouver:

Furuya M. Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs: Thermal-Hydraulic, Core-Wide, and Regional Stability Phenomena. [Internet] [Doctoral dissertation]. IOS; 2006. [cited 2019 Dec 14]. Available from: http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120.

Council of Science Editors:

Furuya M. Experimental and Analytical Modeling of Natural Circulation and Forced Circulation BWRs: Thermal-Hydraulic, Core-Wide, and Regional Stability Phenomena. [Doctoral Dissertation]. IOS; 2006. Available from: http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; urn:NBN:nl:ui:24-uuid:9122b230-3bde-4e3e-877e-ab7e02b97120 ; http://resolver.tudelft.nl/uuid:9122b230-3bde-4e3e-877e-ab7e02b97120

20. Treleaven, Ian James. Passive residual heat removal systems for current and future light water reactors.

Degree: MS, Mechanical Engineering, 2013, California State University – Sacramento

 The main problem with nuclear power during a shutdown is that decay heat is still present and needs to be removed to prevent a number… (more)

Subjects/Keywords: Retrofit; Fukushima Daiichi; Natural convection loop; Natural circulation loop; Fuel rod bundle geometry; Nuclear power plant; Nuclear reactor; Boiling water reactor; Pressurized water reactor

…FIGURES Figures Page 1. Figure 2.1 A schematic of a boiling water reactor… …the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR)… …fission. 8 Figure 2.1 A schematic of a boiling water reactor [7]. Figure 2.2 A… …8 2. Figure 2.2 A schematic of a pressurize water reactor… …types of light water reactors and show where they stand in terms of future reactor design and… 

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Treleaven, I. J. (2013). Passive residual heat removal systems for current and future light water reactors. (Masters Thesis). California State University – Sacramento. Retrieved from http://hdl.handle.net/10211.9/2264

Chicago Manual of Style (16th Edition):

Treleaven, Ian James. “Passive residual heat removal systems for current and future light water reactors.” 2013. Masters Thesis, California State University – Sacramento. Accessed December 14, 2019. http://hdl.handle.net/10211.9/2264.

MLA Handbook (7th Edition):

Treleaven, Ian James. “Passive residual heat removal systems for current and future light water reactors.” 2013. Web. 14 Dec 2019.

Vancouver:

Treleaven IJ. Passive residual heat removal systems for current and future light water reactors. [Internet] [Masters thesis]. California State University – Sacramento; 2013. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/10211.9/2264.

Council of Science Editors:

Treleaven IJ. Passive residual heat removal systems for current and future light water reactors. [Masters Thesis]. California State University – Sacramento; 2013. Available from: http://hdl.handle.net/10211.9/2264


University of Wisconsin – La Cross

21. McInerny, Michael C. Impingement and Entrainment of Fishes at Dairyland Power Cooperative's Genoa Site.

Degree: 1980, University of Wisconsin – La Cross

 The impact to the fishery of Navigation Pool No. 9 of the Mississippi River from impingement and entrainment processes by two Dairyland Power Cooperative power… (more)

Subjects/Keywords: La Crosse Boiling Water Reactor (Genoa, Wis.)  – Environmental aspects; Power-plants  – Environmental aspects  – Wisconsin  – Genoa; Dairyland Power Cooperative. Genoa No. 3 (Power plant)  – Environmental aspects

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

McInerny, M. C. (1980). Impingement and Entrainment of Fishes at Dairyland Power Cooperative's Genoa Site. (Thesis). University of Wisconsin – La Cross. Retrieved from http://digital.library.wisc.edu/1793/30641

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):

McInerny, Michael C. “Impingement and Entrainment of Fishes at Dairyland Power Cooperative's Genoa Site.” 1980. Thesis, University of Wisconsin – La Cross. Accessed December 14, 2019. http://digital.library.wisc.edu/1793/30641.

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

MLA Handbook (7th Edition):

McInerny, Michael C. “Impingement and Entrainment of Fishes at Dairyland Power Cooperative's Genoa Site.” 1980. Web. 14 Dec 2019.

Vancouver:

McInerny MC. Impingement and Entrainment of Fishes at Dairyland Power Cooperative's Genoa Site. [Internet] [Thesis]. University of Wisconsin – La Cross; 1980. [cited 2019 Dec 14]. Available from: http://digital.library.wisc.edu/1793/30641.

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

Council of Science Editors:

McInerny MC. Impingement and Entrainment of Fishes at Dairyland Power Cooperative's Genoa Site. [Thesis]. University of Wisconsin – La Cross; 1980. Available from: http://digital.library.wisc.edu/1793/30641

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

22. Radaideh, Majdi Ibrahim Ahmad. Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors.

Degree: MS, Nuclear, Plasma, Radiolgc Engr, 2016, University of Illinois – Urbana-Champaign

 This work introduces a new method to increase the safety of Boiling Water Reactors (BWRs) during the BWR instability and Loss of Coolant Accidents (LOCA).… (more)

Subjects/Keywords: TRAC/RELAP Advanced Computational Engine (TRACE/PARCS); Boiling Water Reactor (BWR) instability; Loss of Coolant Accident (LOCA)

…Without Scram ATWSI Anticipated Transient Without Scram with Instability BWR Boiling Water… …Injection LWR Light Water Reactors PARCS Purdue Advanced Reactor Core Simulator PCT Peak… …Clad Temperature PWR Pressurized Water Reactor RFRD Reverse Flow Restriction Device… …Commission x CHAPTER 1. INTRODUCTION Stability of Boiling Water Reactors (BWRs) is a… …water level in the reactor vessel, and ultimately boron injection. Therefore, this solution is… 

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Radaideh, M. I. A. (2016). Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors. (Thesis). University of Illinois – Urbana-Champaign. Retrieved from http://hdl.handle.net/2142/95259

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):

Radaideh, Majdi Ibrahim Ahmad. “Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors.” 2016. Thesis, University of Illinois – Urbana-Champaign. Accessed December 14, 2019. http://hdl.handle.net/2142/95259.

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

MLA Handbook (7th Edition):

Radaideh, Majdi Ibrahim Ahmad. “Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors.” 2016. Web. 14 Dec 2019.

Vancouver:

Radaideh MIA. Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors. [Internet] [Thesis]. University of Illinois – Urbana-Champaign; 2016. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/2142/95259.

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

Council of Science Editors:

Radaideh MIA. Analysis of reverse flow restriction device to prevent fuel dryout during loss of coolant and instability accidents of boiling water reactors. [Thesis]. University of Illinois – Urbana-Champaign; 2016. Available from: http://hdl.handle.net/2142/95259

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


ETH Zürich

23. Davis, Jeffrey Adam. An analytical and numerical study of condensing vapor bubbles in liquid pools.

Degree: 2004, ETH Zürich

Subjects/Keywords: KERNREAKTORSICHERHEIT (KERNTECHNIK); REAKTORKÜHLUNG (KERNTECHNIK); SIEDEWASSERREAKTOREN, SWR (KERNTECHNIK); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); REACTOR COOLING (NUCLEAR ENGINEERING); BOILING-WATER REACTORS, BWR (NUCLEAR ENGINEERING); info:eu-repo/classification/ddc/333.7; Natural resources, energy and environment

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Davis, J. A. (2004). An analytical and numerical study of condensing vapor bubbles in liquid pools. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/148337

Chicago Manual of Style (16th Edition):

Davis, Jeffrey Adam. “An analytical and numerical study of condensing vapor bubbles in liquid pools.” 2004. Doctoral Dissertation, ETH Zürich. Accessed December 14, 2019. http://hdl.handle.net/20.500.11850/148337.

MLA Handbook (7th Edition):

Davis, Jeffrey Adam. “An analytical and numerical study of condensing vapor bubbles in liquid pools.” 2004. Web. 14 Dec 2019.

Vancouver:

Davis JA. An analytical and numerical study of condensing vapor bubbles in liquid pools. [Internet] [Doctoral dissertation]. ETH Zürich; 2004. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/20.500.11850/148337.

Council of Science Editors:

Davis JA. An analytical and numerical study of condensing vapor bubbles in liquid pools. [Doctoral Dissertation]. ETH Zürich; 2004. Available from: http://hdl.handle.net/20.500.11850/148337


University of Wisconsin – La Cross

24. Vansteenburg, Jeffrey B. Effects of the Dairyland Power Cooperative electrical generating facility on the phycoperiphyton in navigation pool no. 9, Upper Mississippi River.

Degree: 1983, University of Wisconsin – La Cross

 A study was conducted in Navigation Pool No. 9 of the Upper Mississippi River to determine the impact of the thermal effluent from Dairyland Power… (more)

Subjects/Keywords: Dairyland Power Cooperative. Genoa No. 3 (Power plant)  – Environmental aspects; La Crosse Boiling Water Reactor (Genoa, Wis.)  – Environmental aspects; Thermal pollution of rivers, lakes, etc.  – Mississippi River; Power-plants  – Wisconsin  – Genoa  – Environmental aspects; Mississippi River

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Vansteenburg, J. B. (1983). Effects of the Dairyland Power Cooperative electrical generating facility on the phycoperiphyton in navigation pool no. 9, Upper Mississippi River. (Thesis). University of Wisconsin – La Cross. Retrieved from http://digital.library.wisc.edu/1793/11661

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):

Vansteenburg, Jeffrey B. “Effects of the Dairyland Power Cooperative electrical generating facility on the phycoperiphyton in navigation pool no. 9, Upper Mississippi River.” 1983. Thesis, University of Wisconsin – La Cross. Accessed December 14, 2019. http://digital.library.wisc.edu/1793/11661.

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

MLA Handbook (7th Edition):

Vansteenburg, Jeffrey B. “Effects of the Dairyland Power Cooperative electrical generating facility on the phycoperiphyton in navigation pool no. 9, Upper Mississippi River.” 1983. Web. 14 Dec 2019.

Vancouver:

Vansteenburg JB. Effects of the Dairyland Power Cooperative electrical generating facility on the phycoperiphyton in navigation pool no. 9, Upper Mississippi River. [Internet] [Thesis]. University of Wisconsin – La Cross; 1983. [cited 2019 Dec 14]. Available from: http://digital.library.wisc.edu/1793/11661.

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

Council of Science Editors:

Vansteenburg JB. Effects of the Dairyland Power Cooperative electrical generating facility on the phycoperiphyton in navigation pool no. 9, Upper Mississippi River. [Thesis]. University of Wisconsin – La Cross; 1983. Available from: http://digital.library.wisc.edu/1793/11661

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


ETH Zürich

25. Szijártó, Rita. Condensation of steam in horizontal pipes - model development and validation.

Degree: 2015, ETH Zürich

Subjects/Keywords: STRÖMUNG IN RÖHREN (FLUIDDYNAMIK); KONDENSATION, KONDENSATOREN, KÜHLER (DAMPFMASCHINEN); THERMOHYDRAULIK (KERNTECHNIK); SIEDEWASSERREAKTOREN, SWR (KERNTECHNIK); KERNREAKTORSICHERHEIT (KERNTECHNIK); NUMERISCHE SIMULATION UND MATHEMATISCHE MODELLRECHNUNG; FLOW IN TUBES, PIPES, CLOSED CONDUITS (FLUID DYNAMICS); CONDENSERS, COOLERS (STEAM ENGINES); THERMAL HYDRAULICS (NUCLEAR ENGINEERING); BOILING-WATER REACTORS, BWR (NUCLEAR ENGINEERING); NUCLEAR REACTOR SAFETY (NUCLEAR ENGINEERING); NUMERICAL SIMULATION AND MATHEMATICAL MODELING; info:eu-repo/classification/ddc/333.7; info:eu-repo/classification/ddc/620; Natural resources, energy and environment; Engineering & allied operations

Record DetailsSimilar RecordsGoogle PlusoneFacebookTwitterCiteULikeMendeleyreddit

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

APA (6th Edition):

Szijártó, R. (2015). Condensation of steam in horizontal pipes - model development and validation. (Doctoral Dissertation). ETH Zürich. Retrieved from http://hdl.handle.net/20.500.11850/155164

Chicago Manual of Style (16th Edition):

Szijártó, Rita. “Condensation of steam in horizontal pipes - model development and validation.” 2015. Doctoral Dissertation, ETH Zürich. Accessed December 14, 2019. http://hdl.handle.net/20.500.11850/155164.

MLA Handbook (7th Edition):

Szijártó, Rita. “Condensation of steam in horizontal pipes - model development and validation.” 2015. Web. 14 Dec 2019.

Vancouver:

Szijártó R. Condensation of steam in horizontal pipes - model development and validation. [Internet] [Doctoral dissertation]. ETH Zürich; 2015. [cited 2019 Dec 14]. Available from: http://hdl.handle.net/20.500.11850/155164.

Council of Science Editors:

Szijártó R. Condensation of steam in horizontal pipes - model development and validation. [Doctoral Dissertation]. ETH Zürich; 2015. Available from: http://hdl.handle.net/20.500.11850/155164

.