Published October 1990 | Version v1
Report Restricted

Life assessment procedures for major LWR [light water reactor] components: Cast stainless steel components

  • 1. EG and G Idaho, Inc., Idaho Falls, ID (USA)

Description

This report presents a procedure for estimating the current condition and residual life of safety-related cast stainless steel components in light water reactors (LWRs). The procedure accounts for loss of fracture toughness caused by thermal embrittlement and includes the following: a review of design and fabrication records, inservice inspection records, and operating history; a fracture mechanics evaluation to determine the required toughness at end-of-life using worst-loads and worst-flaw indications; current and future toughness estimates; and criteria regarding continued service, repair, or replacement of the component being evaluated. The report discusses the available Charpy V-notch impact energy, fracture toughness, tensile strength, fatigue resistance, and fatigue-crack growth data, and presents two methods for assessing the degree of thermal embrittlement: metallurgical evaluation and analytical modeling of inservice degradation. 74 refs., 21 figs., 5 tabs

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC A04/MF A01 - GPO as TI91001739; OSTI; INIS.

Files

Restricted

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

Additional details

Additional titles

Subtitle (English)
Volume 3

Publishing Information

Imprint Pagination
49 p.
Report number
NUREG/CR--5314-Vol.3

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Secondary number(s)
EGG--2562-Vol.3.