Structural Component Fabrication and Characterization of Advanced Radiation Resistant ODS Steel for Next Generation Nuclear Systems
Creators
- 1. KAERI, Daejeon (Korea, Republic of)
Description
In a sodium-cooled fast reactor (SFR), the coolant outlet temperature and peak temperature of the fuel cladding tube will be about 545 .deg. C and 700 .deg. C with 250 dpa of a very high neutron dose rate. To realize this system, it is necessary to develop an advanced structural material having high creep and irradiation resistance at high temperatures. Austenitic stainless steel may be one of the candidates because of good strength and corrosion resistance at the high temperatures, however irradiation swelling severely occurred to 120dpa at high temperatures and this eventually leads to a decrease of the mechanical properties and dimensional stability. Advanced radiation resistant ODS steel (ARROS) has been newly developed for the in-core structural components in SFR, which has very attractive microstructures to achieve both superior creep and radiation resistances at high temperatures [4]. Nevertheless, the use of ARROS as a structural material essentially requires the fabrication technology development for component parts such as sheet, plate and tube. In this study, plates and tubes were tentatively fabricated with a newly developed alloy, ARROS. Microstructures as well as mechanical properties were also investigated to determine the optimized condition of the fabrication processes.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2016 spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2016 spring meeting of the KNS
- Dates
- 11-13 May 2016
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 48048699
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CREEP; DISPERSIONS; FABRICATION; FERRITIC STEELS; MECHANICAL PROPERTIES; RADIATIONS; SODIUM COOLED REACTORS; TUBES
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 4 refs, 4 figs, 1 tab