Mechanical property of China A508-3 steel after neutron irradiation
- 1. China Institute of Atomic Energy, Beijing (China)
Description
Reactor pressure vessel (RPV) is the critical un-changeable component of the reactor during its service lifetime, which prevents the radioactive leak of the nuclear power plant core. The irradiation test (about 10 × 1019 cm-2, E ≥ 1 MeV) of the pressure vessel material of China A508-3 steel in research reactor was carried out, and the mechanics performance tests were carried out after the neutron irradiation, including tensile property and impact property. The results show that the yield strength increases by 83, 108 and 52 MPa, and the tensile strength increases by 58, 61 and 49 MPa at -100, 20 and 288 ℃, respectively. The ductile-brittle transition temperature T41J increases by 68 ℃, and the upper shelf energy decreases by 61 J. Meanwhile, by comparing the property of un-irradiated and irradiated material, after irradiated to the level of 60 a service life, A508-3 steel still meets the reactor operation requirement. (authors)
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 50
- Journal Issue
- 2
- Journal Page Range
- p. 204-207
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 51032833
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CHINA; COMPARATIVE EVALUATIONS; DUCTILE-BRITTLE TRANSITIONS; IMPACT TESTS; IRRADIATION; MECHANICAL PROPERTIES; MEV RANGE; NEUTRONS; PRESSURE RANGE MEGA PA; PRESSURE VESSELS; REACTOR OPERATION; RESEARCH REACTORS; SERVICE LIFE; STEELS; TENSILE PROPERTIES; TRANSITION TEMPERATURE; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; ASIA; BARYONS; CARBON ADDITIONS; CONTAINERS; ELEMENTARY PARTICLES; ENERGY RANGE; EVALUATION; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NUCLEONS; OPERATION; PHYSICAL PROPERTIES; PRESSURE RANGE; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; TESTING; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 5 figs., 3 tabs., 6 refs.; http://dx.doi.org/10.7538/yzk.2016.50.02.0204