HIGH TEMPERATURE HYDRAULIC CHARACTERISTICS OF PRTR FUEL ELEMENTS: 19 ROD CLUSTER AND ROD CONCENTRIC TUBE TYPES
Technical Report
·
OSTI ID:4790105
Three types of 19-rod cluster fuel element designs were tested for the Plutonium Recycle Test Reactor. Two were stainless steel clad with NPD reactor type and fittings. One had seventeen stainless steel clad rods and two Zircaloy- 2 clad rods. A stainless steel concentric tube element was also tested. High temperature tests conducted at approximate PRTR operating conditions disclosed no problems in the general design of the 19 rod clusters or concentric tube types. Bowing and elongation of wire wraps were observed in assemblies in which the same material was not used throughout. (M.C.G.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-16-031207
- OSTI ID:
- 4790105
- Report Number(s):
- HW-57332
- Country of Publication:
- United States
- Language:
- English
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