EPFM verification by a large scale test
- 1. Univ. of Tokyo (Japan)
- 2. Japan Power Engineering and Inspection Corp., Tokyo (Japan)
- 3. Mitsubishi Heavy Industries, Ltd., Takasago (Japan)
- 4. Mitsubishi Heavy Industries, Ltd., Kobe (Japan)
Description
Step B test was carried out as one of the elastic plastic fracture mechanics (EPFR) study in Japanese PTS integrity research project. In step B test bending load was applied to the large flat specimen with thermal shock. Tensile load was kept constant during the test. Estimated stable crack growth at the deepest point of the crack was 3 times larger than the experimental value in the previous analysis. In order to diminish the difference between them from the point of FEM modeling, more precise FEM mesh was introduced. According to the new analysis, the difference considerably decreased. That is, stable crack growth evaluation was improved by adopting precise FEM model near the crack tip and the difference was almost same order as that in the NKS4-1 test analysis by MPA. 8 refs., 17 figs., 5 tabs
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the Joint IAEA/CSNI Specialists' Meeting on Fracture Mechanics Verification by Large-Scale Testing held at Pollard Auditorium, Oak Ridge, Tennessee
- Imprint Pagination
- 893 p.
- Journal Page Range
- p. 201-213.
- Report number
- NUREG/CP--0131
Conference
- Title
- Joint IAEA/CSNI specialists' meeting on fracture mechanics verification by large-scale testing.
- Dates
- 26-29 Oct 1992.
- Place
- Oak Ridge, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26001965
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; CRACK PROPAGATION; CRACKS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; NUMERICAL ANALYSIS; PLATES; PRESSURIZATION; PWR TYPE REACTORS; REACTOR VESSELS; STEEL-MNNIMO; STRAINS; TESTING; THERMAL SHOCK
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CONTAINERS; DEFORMATION; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MANGANESE ALLOYS; MATHEMATICS; MECHANICS; MOLYBDENUM ADDITIONS; NICKEL ADDITIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- ORNL/TM--12413; CONF-9210411--.