Status of fast reactor technology development programme in Korea
Description
The fast reactor technology is one of the most promising options for the electricity generation with efficient utilization of uranium resources and reduced waste. Korea Atomic Energy Research Institute completed the conceptual design of KALIMER in March 2002. Efforts are currently directed towards the development of basic key technologies and advanced fast reactor concepts. A new core design concept with enhanced proliferation resistance has been suggested and the reactor size has been increased from 150 to 600 MWe while maintaining the passive residual heat removal capability. Concept study on the ultra long life cores with power densities higher than the conventional ones has been performed. In this concept, a DUPIC-like fuel fabrication technology is applied to the metallic fuel whenever the limit on the clad integrity is reached. 900 MWt Pb cooled breakeven reactor concept is also being developed. Cooperations with IAEA, OECD/NEA, CEA are on-going. I-NERI Project for studies on passive safety features of sodium cooled reactors has been initiated and participation in the Gen-IV Program is planned. (author)
Additional details
Publishing Information
- Imprint Title
- Technical meeting (TM) to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)'. Technical Working Group on Fast Reactors (TWG-FR) (37th annual meeting). Working material
- Imprint Pagination
- 1025 p.
- Journal Page Range
- p. 635-678
- Report number
- IAEA-TM--26677
Conference
- Title
- Technical meeting to 'Review of national programmes on fast reactors and accelerator driven systems (ADS)
- Acronym
- 37. annual meeting of the Technical Working Group on Fast Reactors (TWG-FR)
- Dates
- 10-14 May 2004
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36078414
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CEA; DESIGN; FBR TYPE REACTORS; FUEL ELEMENTS; IAEA; KAERI; NEA; POWER DENSITY; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR TECHNOLOGY; SODIUM
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FRENCH ORGANIZATIONS; INTERNATIONAL ORGANIZATIONS; KOREAN ORGANIZATIONS; METALS; NATIONAL ORGANIZATIONS; OECD; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY
Optional Information
- Notes
- 25 figs, 5 tabs Imprint:Web site: http://www.iaea.org/inis/aws/fnss/twgfr/working_materials.html
- Secondary number(s)
- TWG-FR--118