Fuel-Element Experience in Pressurized-Water Reactors
- 1 December 1966
- journal article
- research article
- Published by Taylor & Francis in Nuclear Applications
- Vol. 2 (6) , 492-498
- https://doi.org/10.13182/nt66-a27544
Abstract
Fuel-element performance in operating pressurized-water reactors has been excellent. Over 250 000 fuel elements containing UO2, UO2-ThO2, or UO2-PuO2 fuel clad with iron- or zirconium-base alloys have performed reliably over a broad range of operating conditions. Experimental evidence to date suggests that fuel elements for pressurized-water reactors can be subjected to more demanding conditions.Keywords
This publication has 4 references indexed in Scilit:
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- Boron Stainless-Steel Fuel-Element Cladding in the Indian Point ReactorNuclear Applications, 1965
- Performance of Thin-Walled Stainless-Steel-Clad Fuel RodsNuclear Applications, 1965
- Embrittlement of Stainless Steels and Nickel-Based Alloys at High Temperature Induced by Neutron RadiationNature, 1965