Preliminary thermal-hydraulic phenomena investigation during total instantaneous blockage accident for CEFR

Author:

Wang Z.,Cao X.W.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference13 articles.

1. Cao, X.W., 2003. Proposal of a fragmentation model for a melt droplet induced by vapor film collapse. The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10). Seoul, Korea (Paper ID G00102).

2. Kamiyama, K., 2004. Model improvement of the SIMMER-III fast reactor safety analysis safety analysis code to freezing phenomena for molten core materials. The 6th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6). Nara, Japan (Paper ID. N6P029).

3. Summary of the SCARABEE-N subassembly melting and propagation tests with an application to hypothetical total instantaneous blockage in a reactor;Kayser;Nucl. Sci. Eng.,1998

4. Kondo, S., 1994. Current R&D status on material motion and interactions relevant to core disruptive accidents. IAEA/IWGFR Technical Committee Meeting on Material Coolant Interactions and Material Movement and Relocation in LMFRs, pp. 89–101.

5. Kondo, S., et al., 1997. Status and achievement of assessment program for SIMMER-III, a multiphase, multicomponent code for lmfr safety analysis. 8th International Topical Meeting on Nuclear Reactor Thermal-hydraulic, Kyoto, Japan, pp. 1340–1348.

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