Behavior of LWR Fuel During Loss-of-Coolant Accidents

Author:

Nagase Fumihisa

Publisher

Elsevier

Reference51 articles.

1. Pseudobinary zircaloy-oxygen phase diagram;Chung;J. Nucl. Mater.,1979

2. The H-Zr (hydrogen-zirconium) system;Zuzek;Bull. Alloy Phase Diagr.,1990

3. Cladding tube deformation and core emergency cooling in a loss of coolant accident of a pressurized water reactor;Erbacher;Nucl. Eng. Des.,1987

4. Hardy, D.G., 1973. High temperature expansion and rupture behaviour of zircaloy tubing. In: Proceedings of the Topical Meeting on Water Reactor Safety, pp. 254–273. Salt Lake City, UT.

5. Hunt, C.E.L., Foote, D.E., 1976. High temperature strain behaviour of zircaloy-4 and Zr-2.5Nb fuel sheaths. In: Proceedings of the Third International Symposium on Zirconium in the Nuclear Industry, STP 633, pp. 50–65. ASTM.

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