Published January 1977
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Primary coolant pipe rupture study AT(49-24)-0202
Description
Fatigue crack growth rate tests were conducted on 304 stainless steel and 516 carbon steel in a simulated BWR primary water environment. A study was carried out to determine the feasibility of measuring sensitization in type 304 SS by use of an Electrochemical Potentiokinetic Reactivation (EPR) technique, develop correlations between degree of sensitization (as measured electrochemically) and the intergranular stress corrosion cracking (IGSCC) resistance of type 304 SS, and provide technical data for evaluating the degree of sensitization and IGSCC susceptibility of welded components. 27 figures, 8 tables
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Additional details
Publishing Information
- Imprint Title
- Annual report of contract research for the Metallurgy and Materials Research Branch, Division of Reactor Safety Research, fiscal year 1976
- Journal Page Range
- p. 108-156.
- Report number
- NUREG--0185
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9382158
- Subject category
- S36: MATERIALS SCIENCE; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; FATIGUE; REACTOR MATERIALS; STEEL-ASTM-A516
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS