Coupled high fidelity thermal hydraulics and neutronics for reactor safety simulations

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This work is a continuation of previous work on the importance of accuracy in the simulation of nuclear reactor safety transients. This work is qualitative in nature and future work will be more quantitative. The focus of this work will be on a simplified single phase nuclear reactor primary. The transient of interest investigates the importance of accuracy related to passive (inherent) safety systems. The transient run here will be an Unprotected Loss of Flow (ULOF) transient. Here the coolant pump is turned off and the un’SCRAM’ed reactor transitions from forced to free convection (Natural circulation). Results will be presented ... continued below

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Mousseau, Vincent A.; Zhang, Hongbin & Zhao, Haihua September 1, 2008.

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Description

This work is a continuation of previous work on the importance of accuracy in the simulation of nuclear reactor safety transients. This work is qualitative in nature and future work will be more quantitative. The focus of this work will be on a simplified single phase nuclear reactor primary. The transient of interest investigates the importance of accuracy related to passive (inherent) safety systems. The transient run here will be an Unprotected Loss of Flow (ULOF) transient. Here the coolant pump is turned off and the un’SCRAM’ed reactor transitions from forced to free convection (Natural circulation). Results will be presented that show the difference that the first order in time truncation physics makes on the transient. The purpose of this document is to illuminate a possible problem in traditional reactor simulation approaches. Detailed studies need to be done on each simulation code for each transient analyzed to determine if the first order truncation physics plays an important role.

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  • International Conference on the Physics of Reactors,Interlaken Switzerland,09/14/2008,09/19/2008

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  • Report No.: INL/CON-08-14245
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 940060
  • Archival Resource Key: ark:/67531/metadc901692

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Office of Scientific & Technical Information Technical Reports

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  • September 1, 2008

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  • Sept. 27, 2016, 1:39 a.m.

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  • Dec. 5, 2016, 1:21 p.m.

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Mousseau, Vincent A.; Zhang, Hongbin & Zhao, Haihua. Coupled high fidelity thermal hydraulics and neutronics for reactor safety simulations, article, September 1, 2008; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc901692/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.