Published 1991 | Version v1
Report Restricted

Need for ASME code changes for reliable characterization of thermal fatigue cracks in Class 1 components

Description

This paper evaluates the current inspection requirements for detecting and sizing thermal fatigue cracks in major light water reactor components. A review of field experience indicates that several sites in base metal that are susceptible to thermal fatigue damage are not included in the service inspection programs. Current inservice inspection procedures and conventional ultrasonic inspection techniques are not adequate for reliable detection and sizing of thermal fatigue cracks. This paper makes several recommendations for changes in ASME Section 11 inspection requirements. 12 refs

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE91018821; NTIS; INIS; US Govt. Printing Office Dep.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
EGG-M--91100

Conference

Title
11. international conference on structural mechanics in reactor technology.
Dates
18-23 Aug 1991.
Place
Tokyo (Japan).

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Funding organization
Nuclear Regulatory Commission, Washington, DC (United States).
Secondary number(s)
CONF-910817--28.