Published September 1985 | Version v1
Report Restricted

Evaluation of welded and repair-welded stainless steel for LWR service. Semiannual report for October 1984-March 1985. Volume 3, No. 1

Creators

Description

Pacific Northwest Laboratory, under the sponsorship of the Division of Engineering Technology of the US Nuclear Regulatory Commission, is conducting a program to determine a method for evaluating welded and repair-welded stainless steel (SS) piping for light-water reactor service. Validated models, based on experimental data, are being developed to predict microstructural development (e.g., the degree of sensitization) and the stress-corrosion cracking (SCC) resistance in the heat-affected zone of the SS weldments. This program will measure and model the development of a susceptible microstructure as it pertains to welded and repair-welded SS pipe. Empirical correlations between material microstructure and SCC will be determined using constant extension rate tests. The successful completion of these tasks will result in a method for assessing the effects of welding/repairing parameters on the SCC resistance of component-specific nuclear reactor welds/repairs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A04/MF A01 - GPO as TI86000321.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
56 p.
Report number
NUREG/CR--3613-Vol.3-No.1

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17017297
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Progress Report
Descriptors DEI
BWR TYPE REACTORS; MICROSTRUCTURE; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REPAIR; STAINLESS STEELS; STRESS CORROSION; WELDED JOINTS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; COOLING SYSTEMS; CORROSION; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
PNL--4941-Vol.3-No.1.