Published 1991 | Version v1
Book

Cladding inner surface wastage for mixed-oxide LMR fuel pins

  • 1. Westinghouse Hanford Co., Richland, WA (United States)

Description

This paper reports cladding inner surface wastage which was measured on reference fuel pins with stainless steel and D9 cladding irradiated beyond goal burnup in the Fast Flux Test Facility. Measurements were compared to the Experimental Breeder Reactor No. 2 based fuel-cladding chemical interaction correlation developed for uranium-plutonium oxide fuels with 20% cold-worked stainless steel cladding. The fuel-cladding chemical interaction was also measured in fuel pins irradiated with HT9 cladding. Comparison of the measurements with the design correlation showed the correlation adequately accounted for the extent of interaction in the Fast Flux Test Facility fuel pins with cold-worked stainless steel, D9, and HT9 cladding

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
ISBN
0-89448-157-6
Imprint Title
Proceedings of LMR
Imprint Pagination
348 p.
Journal Page Range
p. 170-175.

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
11-16 Nov 1990.
Place
Washington, DC (United States).

Optional Information

Secondary number(s)
CONF-901101--.