REA 3D-dynamic analysis in Almaraz NPP with RELAP5/PARCS v2.7 and SIMTAB cross-sections tables-Reference-Cited by-同舟云学术

REA 3D-dynamic analysis in Almaraz NPP with RELAP5/PARCS v2.7 and SIMTAB cross-sections tables

Published:2011-11 Issue:8 Volume:53 Page:1167-1180
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Barrachina T.,Garcia-Fenoll M.,Ánchel F.,Miró R.,Verdú G.,Pereira C.,da Silva C.,Ortego A.,Martínez-Murillo J.C.

Funder

Almaraz-Trillo AIE

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference10 articles.

1. Barrachina, T., Garcia-fenoll, M., Ánchel, F., Miró, R., Verdú, G., 2010. "Analysis of the rod ejection accident with the coupled code RELAP5/PARCS v2.7 in Almaraz NPP", WRFPM 2010/TOP-FUEL Conference, Orlando, USA.

2. CRISSUE-S Partners, 2004. CRISSUE-S WP1-Report, Neutronics/Thermalhydraulics coupling in LWR Technology: Data Requirements and Databases Needed for transient simulations and Qualification.

3. SIMULATE-3. Advanced three-dimensional two-group reactor analysis code;Cronin,1995

4. Downar, T., Lee, D., Xu, Y., Kozlowski, T., Staundenmier, J., 2004. PARCSV2.6 US NRC Core Neutronics Simulator.

5. Fraikin, R., 1997. PWR benchmark on uncontrolled rods withdrawal at zero power, NEA/NSC/DOC(96)20.

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