Published 2004 | Version v1
Report

Status of fast reactor technology development programme in Korea

Creators

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

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)

Part of:
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

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