Published 1984 | Version v1
Report Open

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.

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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