Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13

Author:

Wang Shibao,Mikityuk Konstantin,Dorde Petrovic,Zhang Dalin,Su Guanghui,Qiu Suizheng,Tian Wenxi

Funder

National Natural Science Foundation of China

International Atomic Energy Agency

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. American National Standard for Decay Heat Power in Light Water Reactors, 1979. American Nuclear Society publication ANSI/ANS-5.1.

2. Analysis of the dynamic behavior of the core;Bergeonneau;Nucl. Sci. Eng.,1990

3. Evaluation of the Initial Isothermal Physics Measurements at the Fast Flux Test Facility, a Prototypic Liquid Metal Fast Breeder Reactor;Bess,2010

4. Cabell, C.P., December 1980. A Summary Description of the Fast Flux Test Facility. HEDL-400, United States.

5. Gauthé P. IAEA CRP on natural convection test in Phenix[R]. Technical Report CEA/DEN/CAD/DER/SESI/ LSMR/NT DO 4. CEA; 2010.

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