Published September 1980 | Version v1
Report Restricted

Investigation and evaluation of cracking incidents in piping in pressurized water reactors. Technical report

Description

This report summarizes an investigation of known cracking incidents in pressurized water reactor plants. Several instances of cracking in feedwater piping in 1979, together with reported cases of stress corrosion cracking at Three Mile Island Unit 1, led to the establishment of the third Pipe Crack Study Group. Major differences between the scope of the third PCSG and the previous two are: (1) the emphasis given to systems safety implications of cracking, and (2) the consideration given all cracking mechanisms known to affect PWR piping, including the failure of small lines in secondary safety systems. The present PCSG reviewed existing information on cracking of PWR pipe systems, either contained in written records of collected from meetings in the United States, and made recommendations in response to the PCSG charter questions and to othe major items that may be considered to either reduce the potential for cracking or to improve licensing bases

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A11/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
246 p.
Report number
NUREG--0691

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12641468
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
CRACKS; FATIGUE; INSPECTION; PIPES; PWR TYPE REACTORS; STRESS CORROSION
Descriptors DEC
CHEMICAL REACTIONS; CORROSION; MECHANICAL PROPERTIES; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS