A comparison of thermal hydraulic models for pressurized water reactors

Persistent Link:
http://hdl.handle.net/10150/278320
Title:
A comparison of thermal hydraulic models for pressurized water reactors
Author:
Stanley, Thomas Patrick, 1963-
Issue Date:
1993
Publisher:
The University of Arizona.
Rights:
Copyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.
Abstract:
This thesis compares a new dynamic moving boundary thermal hydraulics fuel pin model (FUELPIN) to a known thermal hydraulics code (COBRA) for the following relationships: (1) Minimum Departure from Nucleate Boiling Ratio (MDNBR) versus time for transient conditions in a Pressurized Water Reactor (PWR) channel, and (2) Position of Minimum DNBR versus time for transient conditions. Relationships between MDNBR and position of MDNBR versus time were analyzed by comparing: (1) output of COBRA, a steady state thermal hydraulics model, with inputs from a PWR simulation code (CEPAC-L), (2) output of CEPAC-L linked FUELPIN. CEPAC-L computer model was shown to be a good simulation of a PWR during steady state conditions and a loss of all primary coolant flow casualty by comparison with an accepted PWR simulation code (CEPAC). FUELPIN was shown to predict larger thermal margins than COBRA for loss of all primary coolant flow transients in PWRs.
Type:
text; Thesis-Reproduction (electronic)
Keywords:
Engineering, Nuclear.
Degree Name:
M.S.
Degree Level:
masters
Degree Program:
Graduate College
Degree Grantor:
University of Arizona
Advisor:
Seale, Robert L.

Full metadata record

DC FieldValue Language
dc.language.isoen_USen_US
dc.titleA comparison of thermal hydraulic models for pressurized water reactorsen_US
dc.creatorStanley, Thomas Patrick, 1963-en_US
dc.contributor.authorStanley, Thomas Patrick, 1963-en_US
dc.date.issued1993en_US
dc.publisherThe University of Arizona.en_US
dc.rightsCopyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.en_US
dc.description.abstractThis thesis compares a new dynamic moving boundary thermal hydraulics fuel pin model (FUELPIN) to a known thermal hydraulics code (COBRA) for the following relationships: (1) Minimum Departure from Nucleate Boiling Ratio (MDNBR) versus time for transient conditions in a Pressurized Water Reactor (PWR) channel, and (2) Position of Minimum DNBR versus time for transient conditions. Relationships between MDNBR and position of MDNBR versus time were analyzed by comparing: (1) output of COBRA, a steady state thermal hydraulics model, with inputs from a PWR simulation code (CEPAC-L), (2) output of CEPAC-L linked FUELPIN. CEPAC-L computer model was shown to be a good simulation of a PWR during steady state conditions and a loss of all primary coolant flow casualty by comparison with an accepted PWR simulation code (CEPAC). FUELPIN was shown to predict larger thermal margins than COBRA for loss of all primary coolant flow transients in PWRs.en_US
dc.typetexten_US
dc.typeThesis-Reproduction (electronic)en_US
dc.subjectEngineering, Nuclear.en_US
thesis.degree.nameM.S.en_US
thesis.degree.levelmastersen_US
thesis.degree.disciplineGraduate Collegeen_US
thesis.degree.grantorUniversity of Arizonaen_US
dc.contributor.advisorSeale, Robert L.en_US
dc.identifier.proquest1352392en_US
dc.identifier.bibrecord.b27056922en_US
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