Evaluation of welded and repair-welded stainless steel for LWR service. Annual report, October 1984-September 1985. Volume 3, No. 2
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 microstructure evolution (e.g., the degree of sensitization, trace element segregation, degree of deformation, etc.) and the stress-corrosion cracking (SCC) resistance of the heat-affected zone (HAZ) of the SS weldments. Thus, the program is concerned with measuring and modeling the development of a SCC-susceptible microstructure in welded and repair-welded SS pipe. Successful completion of the program will result in a method for assessing the effects of welding/repairing parameters on the SCC resistance of component-specific nuclear reactor welds/repairs. This report describes the progress of these studies during the 1985 fiscal year
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A06/MF A01 - GPO as TI87001350.
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Additional details
Publishing Information
- Imprint Pagination
- 112 p.
- Report number
- NUREG/CR--3613-Vol.3-No.2
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18052485
- 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; EVALUATION; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR MATERIALS; REPAIR; STAINLESS STEELS; WELDED JOINTS; WELDING
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; FABRICATION; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; JOINTS; MATERIALS; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- PNL--4941-Vol.3-No.2.