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Boiling water reactor pressure vessel life extension

Conference · · Proc. Am. Power Conf.; (United States)
OSTI ID:6671902
The reactor pressure vessel (RPV) is one of the components which is critical to a potential nuclear power plant life extension. Previous EPRI research has indicated that plant life extension may be feasible, even assuming wholesale replacement of a pressurized water reactor RPV. This paper describes the results of a service life extension study for an operating boiling water reactor (BWR) vessel. The study was conducted under a BWR pilot plant program sponsored in part by EPRI and the Department of Energy. The purpose of the investigation was to identify the probable RPV life limiting effects, and the potential for extending life.
Research Organization:
Multiple Dynamics Corp., Southfield, MI
OSTI ID:
6671902
Report Number(s):
CONF-860422-
Conference Information:
Journal Name: Proc. Am. Power Conf.; (United States) Journal Volume: 48
Country of Publication:
United States
Language:
English