Evaluation of the vent header crack at Edwin I. Hatch Unit number2 Nuclear Power Station
Description
A metallurgical failure analysis was performed on pieces of the cracked vent header pipe from the Edwin I. Hatch Unit 2 Nuclear Power Plant. The analysis consisted of optical microscopy, chemical analysis, mechanical charpy impact testing and fractography. The general conclusions drawn from this analysis were: 1) the material of the vent header met the mechanical and chemical properties of ASTM A516 Gr. 70 material and that the microstructures were consistent with this material; 2) the fracture faces of the cracked pipe were predominantly brittle in appearance with no evidence of fatigue contribution; 3) the NDTT (Nil Ductility Transition Temperature) for this material is approximately -600F (-510C); and 4) the fact that the material's NDTT is significantly out of the normal operating range of the pipe suggests that an impingement of low temperature nitrogen (caused by a faulty torus inerting system) induced a thermal shock in the pipe which, when cooled below its NDTT, cracked in a brittle manner
Additional details
Publishing Information
- Publisher
- American Society for Metals.
- Imprint Place
- Metals Park, OH (USA)
- Imprint Title
- Analyzing failures: The problems and the solutions
- Journal Page Range
- p. 151-158.
Conference
- Title
- International conference and exhibition on fatigue, corrosion cracking, fracture mechanic and failure analysis.
- Dates
- 2-6 Dec 1985.
- Place
- Salt Lake City, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18061682
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRITTLENESS; CHARPY TEST; CHEMICAL ANALYSIS; CHEMICAL PROPERTIES; CRACKS; EVALUATION; FAILURE MODE ANALYSIS; FRACTOGRAPHY; FRACTURE MECHANICS; FRACTURE PROPERTIES; HATCH-2 REACTOR; MICROSTRUCTURE; NITROGEN; REACTOR MATERIALS; REACTOR SAFETY; TEMPERATURE DEPENDENCE; THERMAL SHOCK
- Descriptors DEC
- BWR TYPE REACTORS; CRYSTAL STRUCTURE; DESTRUCTIVE TESTING; ELEMENTS; ENRICHED URANIUM REACTORS; IMPACT TESTS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MECHANICS; NONMETALS; POWER REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS