Accident analyses and passive measures reducing the consequences of a core-melt in CAPRA/CADRA reactor cores-Reference-Cited by-同舟云学术

Accident analyses and passive measures reducing the consequences of a core-melt in CAPRA/CADRA reactor cores

Published:2000-12 Issue:2-3 Volume:202 Page:311-324
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Maschek W,Struwe D

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

Reference23 articles.

1. Barré, B., 1998. The Future of CAPRA. 5th Int. CAPRA Seminar, Karlsruhe

2. Endo, H., Kawashima, M., Suzuki, M., Ninokata, H., Sawada, T., Shimizu, A., Fujii-e, Y., 1996. Safety Characteristics of the SCENES Core, GENES-2, Tsuruga, Japan

3. Heusener, G., Hubert, G., Mitchell, C.M., 1994. EFR Safety Concept, ARS'94, Pittsburgh, USA

4. Ieda, Y., Niwa, H., Uto, N., Kondo, S., 1994. Assessment of Proposed Passive Prevention and Mitigation Measures for Future Fast Breeder Reactors, ARS'94, Pittsburgh, USA

5. Imke, U., Struwe, D., Niwa, H., Sato, I., Camous, F., Moxon, D., 1994. Transient Fuel-Pin Behavior and Failure Conditions in the CABRI-2 In-Pile Tests. Proc. Int. Top. Mtg. Sodium Cooled Fast Reactor Safety, Vol, Obninsk, Russia

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