Calculation of radiation-induced deformation of SUS 316 in the ITER-relevant condition
Creators
Description
SUS 316 stainless steel will be used in ITER as a major structural material. However, accumulation of radiation-induced deformation data in the anticipated operation temperature range, centered at about 300 deg. C, is not adequate. Although it will be used mainly in annealed condition, cold-working and consequent introduction of network dislocations is inevitable at various parts of the structure. Computer simulation was performed to examine the radiation-induced deformation of SUS 316 steel, with emphasis on the effect of network dislocation density, for the ITER-relevant condition. Irradiation creep rates and radiation-induced stress relaxation behaviors were examined at 300 deg. C for various displacement rates, applied stresses and network dislocation densities. Rather complicated dependence on dislocation density has been predicted in both creep deformation and stress relaxation. This complexity results from a competitive redistribution of point defects to the operating deformation mechanisms and from the predominance among them that depends on the network dislocation density
Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2004.04.106;
- PII
- S002231150400234X;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 329-333
- Journal Issue
- 1
- Journal Page Range
- p. 597-601
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 11. International conference on fusion reactor materials
- Acronym
- ICFRM-11
- Dates
- 7-12 Dec 2003
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36030056
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; COLD WORKING; COMPUTERIZED SIMULATION; CREEP; DEFORMATION; DISLOCATIONS; IRRADIATION; ITER TOKAMAK; POINT DEFECTS; STAINLESS STEEL-316; STRESS RELAXATION; STRESSES; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CLOSED PLASMA DEVICES; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAT TREATMENTS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; MATERIALS; MATERIALS WORKING; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; RELAXATION; SIMULATION; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TEMPERATURE RANGE; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2004 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.