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Low exposure irradiation of an enriched seven-rod cluster in KER Loop 1, PR-IP-246-A: Final report

Technical Report ·
DOI:https://doi.org/10.2172/10175828· OSTI ID:10175828
One of the early candidate fuel elements for the N Reactor was the seven-rod cluster fuel element. An objective of the program to determine the suitability of the seven-rod cluster fuel element for N Reactor use was to evaluate the irradiation performance of coextruded, Zircaloy-2-clad, seven-rod cluster fuel elements over a range of exposures from low exposures to high exposures. This report describes the irradiation testing of an enriched seven-rod cluster fuel element which was irradiated to 520 MWD/r.
Research Organization:
General Electric Co., Richland, WA (United States). Hanford Atomic Products Operation
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
10175828
Report Number(s):
HW--74406; ON: DE94017270
Country of Publication:
United States
Language:
English