An assessment of the failure rate for the beltline region of PWR pressure vessels during normal operation and certain transient conditions, Volume 88, Issues 10-778
Ronald Gamble, J. Strosnider, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Engineering
Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, 1981 - Technology & Engineering - 90 pages
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FURTHER DISCUSSION SUMMARY AND CONCLUSIONS
APPENDIX B Improved Monte Carlo Simulation of Rare Event Failures
associated beltline region Beltline Shell beltline weld calculated failure rate computer code Constant Failure Rate copper content crack depth curves discrete random variable EFPY and EOL EFPY Fluence EOL Fluence estimate evaluated failure probability Failure-Rate Pressure/Temperature Paths flaw location flaw-induced fracture fluence levels fracture mechanics models fracture resistance indicate linear elastic low-temperature/pressure transients Marshall preservice flaw minimum detectable flaw neutron fluence neutron irradiation neutron-fluence level corresponding normal distribution normal operation normal startup nuclear pressure vessels Nuclear Regulatory Commission obtained OCTAVIA code OCTAVIA EOL operating PWRs Operation at EOL operational events parametric studies phosphorus preservice flaw distributions pressure transients PWR pressure vessels random variables range rate vs upper-shelf reactor pressure vessels reactor vessel reference variable condition resistance to flaw-induced shutdown operation startup and shutdown Study for Full-Power thermal stress transition temperature region transition-temperature region truncated normal distribution U.S. Nuclear Regulatory upper-shelf energy upper-shelf temperature region vessel wall weld volume