Failure behavior of Zircaloy-4 cladding after oxidation and water quench

Journal of Nuclear Materials

Volumn 362, Issue 1, 2007, Pages 36-45

  Kim, Jun Hwan ^a   Lee, Myoung Ho ^a   Choi, Byoung Kwon ^a   Jeong, Yong Hwan ^a  

^a Korea Atomic Energy Research Institute   (South Korea)

Author keywords

C0500; C0800; F0600; S0100; Z0100

Indexed keywords

CLADDING (COATING); COMPUTER SIMULATION; DUCTILITY; FAILURE ANALYSIS; MECHANICAL TESTING; NUCLEAR REACTORS; OXIDATION;

FAILURE BEHAVIOR; RING COMPRESSION TEST; WATER QUENCHING;

LOSS OF COOLANT ACCIDENTS;

EID: 34247092514     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2006.10.026     Document Type: Article

References (9)

1. Nuclear Regulatory Commission, 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors, 1973.
2. D.O. Hobson, P.L. Rittenhouse, Embrittlement of Zircaloy Clad Fuel Rods by Steam during LOCA Transients ORNL-4758, 1972.
3. H.M. Chung, T.F. Kassner, Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors: Summary Report NUREG/CR-0344, 1980.
4. F. Nagase, T. Fuketa, recent results from LOCA study in JAERI, in: Proceedings of the 2003 Nuclear Safety Research Conference NUREG/CP-0185, 2003.
5. C. Vitanza, Consideration on LOCA Criteria including High Burn-up Effect, SEGFSM Topical Meeting on LOCA Issues, Argonne National Laboratory, May 25-26, 2004.
6. L. Baker, L.C. Just, Studies of Metal-Water Reactions at High Temperatures III. Experimental and Theoretical Studies of the Zirconium-Water Reactions, ANL-6548, 1962.
7. Chung H.M., and Kassner T.F. J. Nucl. Mater. 84 (1979) 327
8. A. Machiels, Perspective on Requirements for Spent Fuel Storage and Transportation, Nuclear Safety Research Conference 2004, 2004.
9. Kim J.H., Choi B.K., Baek J.H., and Jeong Y.H. Nucl. Eng. Des. 236 (2006) 2386