A failure assessment approach for handling combined thermomechanical loading
Description
This paper presents a failure assessment approach for the handling of combined thermomechanical loading of nuclear pressure vessels. The proposed approach is based on a failure assessment curve that accounts for the thermal and mechanical stresses in terms of the elastic stress intensity factor with a plastically corrected crack length. The square of this stress intensity factor divided by the effective elastic modulus is added to a J-integral deformation plasticity solution term. The result is valid for the full range of material/structural behavior, from linear elastic to fully plastic. The fracture behavior parameter, the total J-integral, can then be formulated in terms of a failure assessment curve to account for the combined loading states. The proposed approach was benchmarked using a modified Babcock and Wilson version of the ADINA computer program. The program generated incremental plasticity finite element crack solutions for a single edge cracked plate and a circumferentially flawed cylinder subjected to thermomechanical loadings. The ADINA finite element results agreed quite well with the proposed failure assessment approach. The failure assessment approach is illustrated by a sample problem of a postulated accident condition, based on the occurrence of an overcooling transient (thermal loading) combined with an uncontrolled repressurization (mechanical loading) of a typical nuclear reactor vessel
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- ISBN
- 0-8031-0208-9
- Imprint Title
- Proceedings of the fifteenth national symposium on fracture mechanics
- Journal Page Range
- p. 165-192.
Conference
- Title
- 15. national symposium on fracture mechanics.
- Dates
- 7-9 Jul 1982.
- Place
- College Park, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20057364
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; COOLING; DEFORMATION; DYNAMIC LOADS; ELASTICITY; FAILURE MODE ANALYSIS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; MATERIALS; PLASTICITY; PRESSURE DEPENDENCE; PRESSURE DROP; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR SAFETY; REACTOR VESSELS; STRESS ANALYSIS; STRESS INTENSITY FACTORS; THERMAL STRESSES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; MECHANICAL PROPERTIES; MECHANICS; NUMERICAL SOLUTION; SAFETY; SIMULATION; STRESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS