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U.S. Department of Energy
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Residual life assessment of light water reactor pressure vessels

Conference ·
OSTI ID:5265057
The service-dependent degradation (agina) of light water reactor (LWR) pressure vessels due to irradiation embrittlement is discussed in this paper. The major variable which influence the irradiation embrittlement of LWR vessels are the copper and nickel content of the vessel materials and the fluence. The vessel beltline region is subjected to the largest fluences. A surveillance program, which consists of tensile and Charpy-V-notch (CVN) testing of irradiated specimens of base, heat-affected-zone, and weld materials, is required to monitor changes in their embrittlement. Three main unresolved technical issues are: the limited range and accuracy of the current correlations for caluclating shifts in the reference temperature for nil-ductility transition (RT/sub NDT/) and changes in the Charpy upper shelf energy: the need to demonstrate the conservatism of using CVN-based RT/sub NDT/ shifts for certain sensitive reactor pressure vessel materials; and the type of surveillance program required for any renewed operating license period. The damage caused by irradiation embrittlement can impact plant operating procedures, including heatupcooldown and hydrostatic test procedures, as well as the acceptability of various plant transients. 23 refs., 3 figs., 1 tab
Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA); Cloud (Robert L.) Associates, Inc., Berkeley, CA (USA); California Univ., Santa Barbara (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
5265057
Report Number(s):
EGG-M-15187; CONF-8705275-1; ON: DE88007711
Country of Publication:
United States
Language:
English