skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Cladding inner surface wastage for mixed-oxide liquid metal reactor fuel pins

Conference ·
OSTI ID:6345371

Cladding inner surface wastage 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. 9 refs., 6 figs.

Research Organization:
Westinghouse Hanford Co., Richland, WA (USA)
Sponsoring Organization:
DOE/NE
DOE Contract Number:
AC06-87RL10930
OSTI ID:
6345371
Report Number(s):
WHC-SA-0944; CONF-901101-64; ON: DE91004577; TRN: 91-000955
Resource Relation:
Conference: American Nuclear Society winter meeting, Washington, DC (USA), 11-15 Nov 1990
Country of Publication:
United States
Language:
English

Similar Records

Cladding Profilometry Analysis of Experimental Breeder Reactor-II Metallic Fuel Pins with HT9, D9, and SS316 Cladding
Journal Article · Tue Jan 19 00:00:00 EST 2021 · Energies · OSTI ID:6345371

Fuel/cladding chemical interaction correlation for mixed-oxide fuel pins
Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:6345371

Performance of titanium stabilized D9 cladding and ducts
Conference · Tue Apr 01 00:00:00 EST 1986 · OSTI ID:6345371