Development Status of Surface-Modified Fuel Cladding for ATF
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Korea Hydro and Nuclear Power Central Research Institute, Daejeon (Korea, Republic of)
- 3. KEPCO Nuclear Fuel, Daejeon (Korea, Republic of)
Description
Enhanced accident tolerant fuel (ATF) cladding can be defined as cladding that provides considerably increased response time in the event of a nuclear reactor accident, while providing performance similar to or better than that of the commercial Zr cladding during normal operation. In addition, an enhanced accident tolerance includes suppressed reaction with steam, resulting in lower hydrogen generation, while maintaining acceptable cladding geometry by increasing the strength during accidents. In light water reactors (LWRs), the fuel cladding should have excellent heating transfer and corrosion resistance characteristics, while preventing primary leakage of the fission products in fuel pellet. The major benefit of the surface-modified Zr cladding concept or coated cladding is the economics when compared to other concepts such as FeCrAl cladding, Mo-lined cladding, and SiCf/SiC cladding, because the commercial Zr-based alloy and manufacturing facility can be used continuously. However, the surface-modified Zr and cladding coating concepts require the development of coating materials and coating technology.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Spring Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [3 p.]
Conference
- Title
- 2018 Spring Meeting of the KNS
- Dates
- 16-18 May 2018
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50059320
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CLADDING; KAERI; MANUFACTURING; MODIFICATIONS; PERFORMANCE; REACTOR ACCIDENTS; SURFACES; WATER COOLED REACTORS; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ACCIDENTS; ALLOYS; DEPOSITION; KOREAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; REACTORS; SURFACE COATING; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- 10 refs, 2 figs, 1 tab