Extended-burnup LWR (light-water reactor) fuel [electronic resource] : The amount, characteristics, and potential effects on interim storage.

The results of a study on extended-burnup, light-water reactor (LWR) spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory for the US Department of Energy (DOE). The purpose of the study was to collect and evaluate information on the status of in-reactor pe...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Richland, Wash. : Oak Ridge, Tenn. : Pacific Northwest National Laboratory (U.S.) ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1989.
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Summary:The results of a study on extended-burnup, light-water reactor (LWR) spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory for the US Department of Energy (DOE). The purpose of the study was to collect and evaluate information on the status of in-reactor performance and integrity of extended-burnup LWR fuel and initiate the investigation of the effects of extending fuel burnup on the subsequent handling, interim storage, and other operations (e.g., rod consolidation and shipping) associated with the back end of the fuel cycle. The results of this study will aid DOE and the nuclear industry in assessing the effects on waste management of extending the useful in-reactor life of nuclear fuel. The experience base with extended-burnup fuel is now substantial and projections for future use of extended-burnup fuel in domestic LWRs are positive. The basic performance and integrity of the fuel in the reactor has not been compromised by extending the burnup, and the potential limitations for further extending the burnup are not severe. 104 refs., 15 tabs.
Item Description:Published through the Information Bridge: DOE Scientific and Technical Information.
03/01/1989.
"pnl-6717"
"DE89009715"
Bailey, W.J.