Irradiation induced tensile property change of SA 508 Cl.3 reactor pressure vessel steels
Creators
- 1. Nuclear Materials Technology Development Team, Korea Atomic Energy Research Institute (Korea, Republic of)
- 2. Nuclear Materials Technology Development Team, Korea Atomic Energy Research Institute (KR)
Description
Irradiation induced tensile property change of four kinds of reactor pressure vessel steels manufactured by different steel refining process was compared based on the differences in the unirradiated and irradiated microstructure. Microvickers hardness, indentation, and miniature tensile specimen tests were conducted for mechanical property measurement and optical microscope (OM) and transmission electron microscope (TEM) were used for microstructural characterization. Specimens were 2 irradiated to a neutron fluence of 2.7x1019n/cm2 (E ≥ 1 MeV) at 288 deg. C. Investigation on the unirradiated microstructures showed largely a same microstructure in that tempered acicular bainite and ferrite with bainitic phase prevailing in the unirradiated condition. Band-shaped segregations were also clearly observed except a kind of materials. A large difference in the unirradiated microstructure appeared in the grain size and carbide microstructure. Of carbide microstructures, noticeable differences were observed in the size and distribution of cementite, and bainitic lath microstructures. No noticeable changes were observed in the optical and thin film TEM microstructures after irradiation. Complicated microstructural. state of heat treated bainitic low alloy microstructure prevents easy quantification of microstructural changes due to irradiation. Apparent differences, however, were observed in the results of mechanical testing. Results of tensile testing and hardness measurement show that a steel refined by vacuum carbon deoxidation(VCD) method exhibits the highest radiation hardening behavior. Some of mechanical testing results on irradiated materials were possible to understand based on the initial microstructure, but further investigations using a wide array of sophisticated tools (for example, SANS, APFIM) are required to understand and characterize irradiation induced defects that are responsible for irradiation hardening behavior but are not revealed by conventional TEM. (author)
Files
36024341.pdf
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Additional details
Publishing Information
- Imprint Title
- IGORR 6: Proceedings of the 6th meeting of the International Group On Research Reactors
- Imprint Pagination
- 539 p.
- Journal Page Range
- p. 455-477
- Report number
- KAERI/GP--128/98
Conference
- Title
- 6. meeting of the International Group On Research Reactors
- Acronym
- IGORR 6
- Dates
- 29 Apr - 1 May 1998
- Place
- Taejon (Korea, Republic of)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36024341
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MECHANICAL PROPERTIES; MICROSTRUCTURE; OPTICAL MICROSCOPES; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; STEELS; TRANSMISSION ELECTRON MICROSCOPY; VICKERS HARDNESS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ELECTRON MICROSCOPY; IRON ALLOYS; IRON BASE ALLOYS; MICROSCOPES; MICROSCOPY; RADIATION EFFECTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 19 refs, 6 figs, 3 tabs
- Secondary number(s)
- INIS-XA-C--027