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. ...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.展开更多
The study gives a brief introduction on development of innovated nuclear system in China,mainly focus on the materials R&D status for the sodium cooled fast reactor.With the high speed development of economy,China...The study gives a brief introduction on development of innovated nuclear system in China,mainly focus on the materials R&D status for the sodium cooled fast reactor.With the high speed development of economy,China needs a huge energy supply;at same time a more cleaning energy to reduce the carbon release is demanded.The nuclear energy is the most cleaning energy at present time,especially the innovated nuclear system which is so-called GenerationⅣpower plants has got its prior development due to its safety, economical and little fission production produced.Fast breeder reactor,as the priority development reactor type in the Gen-Ⅳnuclear system,is the key to the advanced closed fuel cycle technologies.China experimental fast reactor(CEFR ) has been completed the design,construction the synthesis system commissioning and reached its physical criticality on July 21,2010.At China Institute of Atomic Energy,the CEFR and other research facilities have been established,and extensive studies are planning to carry out in the areas of fuel and materials development.This will laid the foundation for the design and development of the future's CFR—900(China Demonstration Fast Reactor) and CCFR(China Commercial Fast Reactor). Highlights of some of materials R&D studies are discussed in this paper.展开更多
钠冷快堆(Sodium-cooled Fast Reactor,SFR)作为第四代核能系统的代表性堆型,凭借其燃料增殖潜力、次锕系核素嬗变能力及固有安全特性成为国际研究热点。然而,钠冷快堆设计与运行过程中普遍存在核数据随机性、模型简化误差、边界条件扰...钠冷快堆(Sodium-cooled Fast Reactor,SFR)作为第四代核能系统的代表性堆型,凭借其燃料增殖潜力、次锕系核素嬗变能力及固有安全特性成为国际研究热点。然而,钠冷快堆设计与运行过程中普遍存在核数据随机性、模型简化误差、边界条件扰动等多源不确定性,上述不确定性与反应堆内复杂的中子学行为、钠热工水力特性及事故工况下的多物理场效应耦合传播,可能导致钠冷快堆系统响应偏离或异常波动,甚至引发事故风险。本文主要从核反应堆物理计算、热工水力分析和事故安全分析三个方向概述了钠冷快堆系统不确定性分析的研究进展,总结了国际范围内的研究成果,分析了遇到的技术挑战和未来研究的发展趋势,并探讨了我国在这些领域的研究现状及未来的研究方向。通过分析与总结,希望为未来钠冷快堆系统的安全性评估与设计优化提供一定参考。展开更多
文摘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.
文摘The study gives a brief introduction on development of innovated nuclear system in China,mainly focus on the materials R&D status for the sodium cooled fast reactor.With the high speed development of economy,China needs a huge energy supply;at same time a more cleaning energy to reduce the carbon release is demanded.The nuclear energy is the most cleaning energy at present time,especially the innovated nuclear system which is so-called GenerationⅣpower plants has got its prior development due to its safety, economical and little fission production produced.Fast breeder reactor,as the priority development reactor type in the Gen-Ⅳnuclear system,is the key to the advanced closed fuel cycle technologies.China experimental fast reactor(CEFR ) has been completed the design,construction the synthesis system commissioning and reached its physical criticality on July 21,2010.At China Institute of Atomic Energy,the CEFR and other research facilities have been established,and extensive studies are planning to carry out in the areas of fuel and materials development.This will laid the foundation for the design and development of the future's CFR—900(China Demonstration Fast Reactor) and CCFR(China Commercial Fast Reactor). Highlights of some of materials R&D studies are discussed in this paper.
文摘钠冷快堆(Sodium-cooled Fast Reactor,SFR)作为第四代核能系统的代表性堆型,凭借其燃料增殖潜力、次锕系核素嬗变能力及固有安全特性成为国际研究热点。然而,钠冷快堆设计与运行过程中普遍存在核数据随机性、模型简化误差、边界条件扰动等多源不确定性,上述不确定性与反应堆内复杂的中子学行为、钠热工水力特性及事故工况下的多物理场效应耦合传播,可能导致钠冷快堆系统响应偏离或异常波动,甚至引发事故风险。本文主要从核反应堆物理计算、热工水力分析和事故安全分析三个方向概述了钠冷快堆系统不确定性分析的研究进展,总结了国际范围内的研究成果,分析了遇到的技术挑战和未来研究的发展趋势,并探讨了我国在这些领域的研究现状及未来的研究方向。通过分析与总结,希望为未来钠冷快堆系统的安全性评估与设计优化提供一定参考。
