Radiation damage in stainless steel under varying temperature neutron irradiation
Creators
- 1. Kyushu Univ., Kasuga, Fukuoka (Japan). Research Inst. for Applied Mechanics
Description
Microstructural evolution of model alloys of 316SS was examined by neutron irradiation at JMTR under cyclic temperature varying condition. In the case of Fe-16Cr-17Ni, formation of interstitial loops and voids are strongly suppressed by varying the temperature from 473K to 673K. By adding Ti as miner element (0.25wt%), however, abnormal accumulation of vacancies (void swelling of 11%dpa at 0.1dpa) was observed. Theoretical analysis standing on the rate theory of defect clustering and simulation irradiation experiments with heavy ions indicates that the vacancy-rich condition which appears temporally during and after changing the temperature from low to high brings these results. It was also shown that only 1 dpa pre-irradiation at low temperature changes swelling behavior at high temperature above several 10 dpa. The understanding of non-steady-state defect processes under temperature varying irradiation is very important to estimate the radiation damage under fusion environment where short-term and long-term temperature variation is expected. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the first symposium on utilization of research reactors and JMTR
- Imprint Pagination
- 203 p.
- Journal Page Range
- p. 44-58
- Report number
- JAERI-Conf--98-007
Conference
- Title
- 1. symposium on utilization of research reactors and JMTR
- Dates
- 29-30 Sep 1997
- Place
- Mito, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 29053537
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC DISPLACEMENTS; FIRST WALL; INTERSTITIALS; IRRADIATION; JMTR REACTOR; NEUTRONS; STAINLESS STEEL-316; SWELLING; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; TITANIUM ADDITIONS; VACANCIES; VOIDS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BARYONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DEFORMATION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUCLEONS; PHYSICAL RADIATION EFFECTS; POINT DEFECTS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS