Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/100

Author:

Guo Chao,Lu Daogang,Zhang Xun,Sui Danting

Funder

International Atomic Energy Agency

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference11 articles.

1. Cacuci, D.G., 2010. Handbook of Nuclear Engineering. In: Rouault, J. et al. (Ed.), Sodium Fast Reactor Design: Fuels, Neutronics, Thermal–Hydraulics, Structural Mechanics and Safety, pp. 2321–2710.

2. GIF, 2002. Generation IV Technology Roadmap, Report GIF-002-00.

3. SAC-CFR computer code verification with experimental breeder reactor II loss-of-primary-flow-without-scram tests data;Guo;J. Ann. Nucl. Energy,2014

4. Numerical Solution of the One-energy, Space-Independent Reactor Kinetics Equations for Neutron Density Given the Excess Reactivity;Kaganove,1960

5. A solution to the turbulent Graetz-problem–III. Fully developed and entrance region heat transfer rates;Notter;J. Chem. Eng. Sci.,1972

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