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Preliminary evaluation of licensing issues associated with U. S. -sited CANDU-PHW nuclear power plants

Technical Report ·
DOI:https://doi.org/10.2172/5159681· OSTI ID:5159681
The principal safety-related characteristics of current CANDU-PHW power plants are described, and a distinction between those characteristics which are intrinsic to the CANDU-PHW system and those that are not is presented. An outline is given of the main features of the Canadian safety and licensing approach. Differences between the U.S. and Canadian approach to safety and licensing are discussed. Some of the main results of the safety analyses, routinely performed for CANDU-PHW reactors, are presented. U.S.-NRC General Design Criteria are evaluated as regards their applicability to CANDU-PHW reactors; vice-versa the CANDU-PHW reactor is evaluated with respect to its conformance to the U.S.-NRC General Design Criteria. A number of design modifications are proposed to be incorporated into the CANDU-PHW reactor in order to facilitate its introduction into the U.S.
Research Organization:
Argonne National Laboratory (ANL), Argonne, IL (United States)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
5159681
Report Number(s):
ANL-77-97
Country of Publication:
United States
Language:
English