Self-sufficient nuclear fuel technology development and applications
Creators
- 1. Dongguk University, College of Energy and Environment, 707 Seokjang-Dong, Gyeongju, Gyeongbuk 780-714 (Korea, Republic of)
Description
Highlights: ► Three kinds of nuclear fuel technology development procedures are provided. ► Detailed activities for nuclear fuel and cladding material developments are described. ► Main fuel failure causes for PWRs in Korea and countermeasures are provided. - Abstract: A cutting-edge nuclear fuel technology in Korea has been acquired through four stepwise nuclear fuel technology development phases starting from the 1970s that may include a fuel import phase, a turnkey fuel technology transfer phase, a fuel technology joint-development phase and a self-sufficient fuel technology development phase. The self-sufficient fuel technology development procedures have been applied for developing four kinds of advanced PWR fuels such as PLUS7, 16ACE7, 17ACE7 and HIPER, an advanced cladding material of HANA and various fuel performance analysis computer codes. The PLUS7, 16ACE7 and 17ACE7 fuels have already been implemented on a batch scale in the PWRs operating in Korea. Based on the forty years' operation experience of the PWRs in Korea and various fuel verification/validation test databases acquired from the advanced fuel developments, main fuel failure causes observed in the PWRs seem to be grid-to-rod fretting wear, debris-induced wear and accelerated Zry-4 cladding corrosion. Outstanding countermeasures against such main fuel failures are proposed to accomplish an ultimate goal of zero fuel defects for the aforementioned advanced fuels.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.04.023Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.04.023;
- PII
- S0029-5493(12)00227-0;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 249
- Journal Page Range
- p. 287-296
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 8. international topical meeting on nuclear thermal-hydraulics, operation and safety
- Acronym
- NUTHOS-8
- Dates
- 10-14 Oct 2010
- Place
- Shanghai (China)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43078929
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; COMPUTER CODES; CORROSION; DEFECTS; FUEL ASSEMBLIES; FUEL ELEMENT FAILURE; FUEL RODS; NUCLEAR FUELS; PWR TYPE REACTORS; REPUBLIC OF KOREA; TECHNOLOGY TRANSFER; VALIDATION; WEAR; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-4; ASIA; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; DEVELOPING COUNTRIES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FAILURES; FUEL ELEMENTS; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SURFACE COATING; TESTING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.