Annealing effect of thermal conductivity on thermal stress induced fracture of nuclear graphite
- 1. Dept. of HTTR Project, Japan Atomic Energy Research Inst., Ibaraki-ken (Japan)
- 2. Dept. of Office of Planning, Japan Atomic Energy Research Inst., Chiba-ken (Japan)
- 3. Dept. of Design of Nuclear Power Div., Fuji Electric Systems Co., Ltd., Kanagawa-ken (Japan)
Description
Graphite materials are used for structural components in the core of high temperature gas-cooled reactors (HTGRs) because of their excellent thermo/mechanical properties. When the core temperature is raised at an accident, the thermal stress of the components is induced, and it enhances the fracture probability of them. In general, the thermal conductivity of graphite is decreased by neutron irradiation due to irradiation-induced defects preventing heat conduction by phonon. It is hence expected that decreased thermal conductivity is recovered to some extent by thermal annealing at the accident. Therefore, the consideration of the thermal annealing effect is placed as much important subject in the fracture/strength evaluation of the graphite components at the accident. In the present study, the thermal stress and the fracture probability of graphite components influenced by the thermal annealing were investigated by a finite element method (FEM) analysis. It was shown that the annealing effect decreases the thermal stress and a certain level of the fracture probability. (orig.)
Additional details
Publishing Information
- Journal Title
- Key Engineering Materials
- Journal Volume
- 297-300
- Journal Issue
- pt.1-4
- Series
- Advances in fracture and strength
- Journal Page Range
- p. 1698-1703
- ISSN
- 1013-9826
- CODEN
- KEMAEY
Conference
- Title
- APCFS'04 - advances in fracture and strength
- Dates
- 6-8 Oct 2004
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 36107508
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; FRACTURES; GRAPHITE; HTTR REACTOR; PROBABILITY; REACTOR MATERIALS; THERMAL CONDUCTIVITY; THERMAL STRESSES
- Descriptors DEC
- CALCULATION METHODS; CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FAILURES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT TREATMENTS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; MECHANICS; MINERALS; NONMETALS; NUMERICAL SOLUTION; PHYSICAL PROPERTIES; REACTORS; RESEARCH AND TEST REACTORS; STRESSES; THERMODYNAMIC PROPERTIES