Study of creep deformation of irradiated zircaloy cladding by isothermal heating of irradiated PHWR fuel pins in temperature range 700°C–900°C

Author:

Sah D. N.,Viswanathan U. K.,Anantharaman S.

Publisher

Springer Science and Business Media LLC

Reference11 articles.

1. Hardy D G, “High Temperature Expansion and Rupture Behaviour of Zircaloy Tubing”, ANS Topical Meeting on Water Reactor Safety, Salt Lake City, Utah (1973), conf. paper CONF-730304.

2. Juenke E F and White J F, “Physical -Chemical Studies of Clad UO2 under Reactor Accident Conditions”, General Electric Co, Report GEMP-731 (1970).

3. Emerich K M, Juenke E F and White J F, “Failure of pressurized Zircaloy Tubes during Thermal Excursion in Steam and Inert Atmospheres”, Symposium on Application Related Phenomena in Zirconium and its Alloys, ASTM STP 458, 252 (1969).

4. Morize P, Vidal H, Frenkel J M and Roulliay R, “Zircaloy Cladding Diametral Expansion during LOCA”, CSNI Specialist Meeting on the Behaviour of Water Reactor Fuel Elements under Accident Conditions, Spaatind, Norway (1976).

5. Hunt C E L and Newell W G, “The Ballooning Behaviour of Zircaloy-4 Fuel Sheaths at a Heating Rate of 0.5°C/s” AECL Report No AECL-6342 (1978).

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