The history of LOCA embrittlement criteria.

[1]  W. B. Cottrell.  ECCS rule-making hearing , 1974 .

[2]  T. F. Kassner,et al.  Embrittlement criteria for Zircaloy fuel cladding applicable to accident situations in light-water reactors. Summary report , 1980 .

[3]  Satoru Kawasaki,et al.  Zircaloy-4 Cladding Embrittlement due to Inner Surface Oxidation under Simulated Loss-of-Coolant Condition , 1981 .

[4]  R. A. Lorenz,et al.  Fuel Rod Failure Under Loss-of-Coolant Conditions in Treat , 1970 .

[5]  Satoru Kawasaki,et al.  Embrittlement of zircaloy-4 due to oxidation in environment of stagnant steam. , 1982 .

[6]  J. Abriata,et al.  The H-Zr (hydrogen-zirconium) system , 1990 .

[7]  A Sawatzky.  A proposed criterion for the oxygen embrittlement of Zircaloy-4 fuel cladding , 1979 .

[8]  Satoru Kawasaki,et al.  Failure-Bearing Capability of Oxidized Zircaloy-4 Cladding under Simulated Loss-of-Coolant Condition , 1983 .

[9]  D. O. Hobson.  Ductile-brittle behavior of Zircaloy fuel cladding. , 1972 .

[10]  P. E. MacDonald,et al.  Light water reactor fuel response during reactivity initiated accident experiments , 1979 .

[11]  LABORATORY SIMULATIONS OF CLADDING-STEAM REACTIONS FOLLOWING LOSS-OF- COOLANT ACCIDENTS IN WATER-COOLED POWER REACTORS. , 1970 .

[12]  M. Réocreux,et al.  A study of fuel behavior in PWR design basis accident: an analysis of results from the PHEBUS and EDGAR experiments , 1990 .

[13]  P. L. Rittenhouse,et al.  EMBRITTLEMENT OF ZIRCALOY-CLAD FUEL RODS BY STEAM DURING LOCA TRANSIENTS. , 1972 .

[14]  R. E. Pawel.  Oxygen diffusion in beta zircaloy during steam oxidation , 1974 .