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Status of a Sodium Cooled Fast Reactor Technology Development Program in Korea

Status of a Sodium Cooled Fast Reactor Technology Development Program in Korea

作     者:Chungho Cho Younggyun Kim Jinwook Chang Sang-Ji Kim Chan-Bock Lee Seong-O Kim Jong-Bum Kim Hae-Yong Jeong Yong-Bum Lee Yeong-Il. Kim 

作者机构:Fast Reactor Technology Development Division Korea Atomic Energy Research Institute Daejeon 305-353 Republic of Korea 

出 版 物:《Journal of Energy and Power Engineering》 (能源与动力工程(美国大卫英文))

年 卷 期:2012年第6卷第9期

页      面:1379-1397页

学科分类:082704[工学-辐射防护及环境保护] 082703[工学-核技术及应用] 08[工学] 0827[工学-核科学与技术] 

主  题:钠冷快堆 韩国 技术 状态 原子能研究所 能源资源 概念设计 反应器系统 

摘      要:Korea imports about 97% of its energy resources as its available energy resources are extremely limited. Thus, the role of nuclear power in electricity generation is expected to become more important in future years. A fast reactor system is one of the most promising options for electricity generation with an efficient utilization of uranium resources and a reduction of radioactive wastes. Based on the experiences gained during the development of the conceptual designs for KALIMER (Korea advanced liquid metal reactor), the KAERI (Korea Atomic Energy Research Institute) is currently developing advanced SFR (sodium cooled fast reactor) design concepts that can better meet the Gen Ⅳ (Generation Ⅳ) technology goals. The long-term advanced SFR development plan will be carried out toward the construction of an advanced SFR demonstration plant by 2028. Advanced concept design studies and the development of the advanced SFR technologies necessary for its commercialization and basic key technologies carried out by KAERI are included in this paper.

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