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U.S. Department of Energy
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PROPOSED DESIGN AND MATERIALS EVALUATION PROGRAM FOR ETR 6" X 6" LATTICE FACILITY IN PILE TUBES

Technical Report ·
OSTI ID:4330428
The Engineering Test Reactor will have a considerably higher gamma heating level than the MTR or other reactors in which irradiation testing has been done. The thermal stresses which would result in in-pile tubes in the ETR can not be dealt with by conventional design methods. To meet this situation a proposed design and materials evaluation program for ETR in-pile tubes is presented. (W.L.H.)
Research Organization:
Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
NSA Number:
NSA-12-011857
OSTI ID:
4330428
Report Number(s):
WAPD-PWR-CP-3025
Country of Publication:
United States
Language:
English

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