VISA: a computer code for predicting the probability of reactor pressure-vessel failure. [PWR]
The VISA (Vessel Integrity Simulation Analysis) code was developed as part of the NRC staff evaluation of pressurized thermal shock. VISA uses Monte Carlo simulation to evaluate the failure probability of a pressurized water reactor (PWR) pressure vessel subjected to a pressure and thermal transient specified by the user. Linear elastic fracture mechanics are used to model crack initiation and propagation. parameters for initial crack size, copper content, initial RT/sub NDT/, fluence, crack-initiation fracture toughness, and arrest fracture toughness are treated as random variables. This report documents the version of VISA used in the NRC staff report (Policy Issue from J.W. Dircks to NRC Commissioners, Enclosure A: NRC Staff Evaluation of Pressurized Thermal Shock, November 1982, SECY-82-465) and includes a user's guide for the code.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5723999
- Report Number(s):
- NUREG/CR-3384; PNL-4774; ON: DE84001153
- Country of Publication:
- United States
- Language:
- English
Similar Records
Status of the United States Nuclear Regulatory Commission Pressurized Thermal Shock Rule Re-Evaluation Project
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
V CODES
PRESSURE VESSELS
FRACTURE PROPERTIES
THERMAL SHOCK
PWR TYPE REACTORS
REACTOR ACCIDENTS
FAILURES
HEAT TRANSFER
REACTOR SAFETY
THERMAL STRESSES
ACCIDENTS
CONTAINERS
ENERGY TRANSFER
MECHANICAL PROPERTIES
REACTORS
SAFETY
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled