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U.S. Department of Energy
Office of Scientific and Technical Information

THE DEVELOPMENT AND TESTING OF THE UO$sub 2$ FUEL ELEMENT SYSTEM. Progress Report for Period September 1-December 31, 1959

Technical Report ·
OSTI ID:4147201
A substitution of one quarter hard 304 SS tubing for annealed 347 SS in the Advanced Pressurized Water Reactor (APWR) fuel red resulted in a decrease in cladding thickness of 5 mils. A fuel cycle cost estimate for the APWR is contained. A preliminary cost analysis of fabricating UO/sub 2/ fuel elements by vibratory compaction was made. The thermally acceptable diameter for an are- fused powderpacked fuel rod was in the range of 0.350 plus or minus 0.005 in. for all fuel densities considered (80, 85, 90, and 94%). The use of a metal heat- transfer medium in the gas gap annulus of a pelletized fuel red was investigated. The financial implications of (1) varying the pellet and tube tolerances of a fuel red, (2) varying the gas gap conductivity, and (3) including the contribution of radiation in the thermal calculations were investigated. The economics of a UO/sub 2/ pellet with zoned enrichment are discussed. Preliminary experiments indicated that brazing of empty fuel tubes into cluster formations will have to be done in a vertical position. The feasibility of dip brazing as a fuel red end-closure procedure was established. (For preceding period see NYO2735.) (C.J.G.)
Research Organization:
Combustion Engineering, Inc. Nuclear Div., Windsor, Conn.
NSA Number:
NSA-14-018143
OSTI ID:
4147201
Report Number(s):
NYO-9006
Country of Publication:
United States
Language:
English