Review of Recent ORNL Specific-Plant Analyses
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The Oak Ridge National Laboratory (ORNL) has been helping the Nuclear Regulatory Commission (NRC) develop the pressurized thermal shock (PTS) evaluation methodology since the mid-1970s. During the early 1980s, ORNL developed the integrated PTS (IPTS) methodology, which is a probabilistic approach that includes postulation of PTS transients, estimation of their frequencies, thermal/hydraulic analyses to obtain the corresponding thermal and pressure loadings on the reactor pressure vessel, and probabilistic fracture mechanics analyses. The scope of the IPTS program included development of the probabilistic fracture mechanics code OCA-P and application of the IPTS methodology to three nuclear plants in the US (Oconee I, Calvert Cliffs I, and H. B. Robinson II). The results of this effort were used to help establish the PTS Rule (10CFR50.61) and Regulatory Guide 1.154, which pertains to the PTS issue. The IPTS Program was completed in 1985, and since that time the ORNL related effort has been associated with long-term programs aimed at improving/updating the probabilistic fracture mechanics methodology and input data. In 1990, the NRC requested that ORNL review a vessel-integrity evaluation report submitted to the NRC by the Yankee Atomic Electric Co. for the Yankee Rowe reactor and that ORNL also perform an independent probabilistic fracture mechanics analysis. Details of the methodology and preliminary results are the subject of this paper/presentation.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE; USNRC
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10107835
- Report Number(s):
- CONF-9111133--2; ON: DE92004222
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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FAILURE MODE ANALYSIS
FRACTURE MECHANICS
HEAT TRANSFER
HYDRAULICS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE VESSELS
PRESSURIZATION
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ROWE YANKEE REACTOR
SAFETY ANALYSIS
THERMAL SHOCK
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