Integration of PTS studies to calculate through-the-wall crack probabilities
Description
This paper describes a NRC-sponsored research project formed to help confirm the technical basis for the proposed Pressurized Thermal Shock (PTS) rule, to aid in the development of guidance for licensee plant-specific PTS analyses, and to examine the effects of proposed corrective measures. The research project, still under way (10/84), consists of PTS pilot analyses for three PWRs: Oconee Unit 1, designed by Babcock and Wilcox; Calvert Cliffs Unit 1, designed by Combustion Engineering; and H.B. Robinson Unit 2, designed by Westinghouse. The study team consists of Oak Ridge National Laboratory (ORNL), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Brookhaven National Laboratory (BNL), and Purdue University, with the results being integrated by Oak Ridge National Laboratory (ORNL)
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI85005359.Files
16064782.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- CONF-8410142--75
Conference
- Title
- 12. water reactor safety research information meeting.
- Dates
- 23-26 Oct 1984.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064782
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; HEAT TRANSFER; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; RISK ASSESSMENT; THERMAL SHOCK
- Descriptors DEC
- CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS