吴宜灿;柏云清;宋勇;黄群英;刘超;王明煌;周涛;金鸣;吴庆生;汪建业;蒋洁琼;胡丽琴;李春京;高胜;李亚洲;龙鹏程;赵柱民;郁杰;FDS团队;

• 1:中国科学院核能安全技术研究所

摘要(Abstract)：

针对加速器驱动次临界系统预研装置和第四代铅冷快堆的技术发展目标和实验要求,完成了具有临界和加速器驱动次临界双模式运行能力的10 MW中国铅基研究堆CLEAR-Ⅰ概念设计。CLEAR-Ⅰ采用铅铋合金冷却,利用相对成熟的燃料和材料技术,通过全堆芯遥操自动更换燃料组件实现不同的实验目标,反应堆具有良好的现实可行性、安全可靠性、实验灵活性和技术延续性。本文简要介绍了CLEAR-Ⅰ概念设计参考方案,并总结了反应堆的安全特性和技术研发进展。

关键词(KeyWords)： 加速器驱动次临界系统;中国铅基反应堆;铅铋;研究反应堆;概念设计

Abstract:

Keywords:

基金项目(Foundation): 中国科学院战略性先导科技专项XDA03040000;; 国家自然科学基金重大研究计划重点支持项目91026004

作者(Authors): 吴宜灿;柏云清;宋勇;黄群英;刘超;王明煌;周涛;金鸣;吴庆生;汪建业;蒋洁琼;胡丽琴;李春京;高胜;李亚洲;龙鹏程;赵柱民;郁杰;FDS团队;

参考文献(References)：

• [1]IAEA-TECDOC-985.Accelerator driven systems:Energy generation and transmutation of nuclear waste.Status report[R].November 1997.
• [2]OECD/NEA,Accelerator-driven Systems(ADS)and Fast Reactors(FR)in Advanced Nuclear Fuel Cycles A Comparative Study[R].2002.
• [3]詹文龙,等.未来先进裂变能—ADS嬗变系统[J].中国科学院院刊,2012,27(3):375-381.
• [4]G.Bandini,et al.Thermal-hydraulics analysis of ELSY lead fast reactor with open square core option[J].Nuclear Engineering and Design 241(2011)1165-1171.
• [5]A.Borgohain,et al.Natural circulation studies in a lead bismuth eutectic loop[J].Progress in Nuclear Energy 53(2011)308-319.
• [6]Tsuyoshi Okawa,et al.Design Study on Pb-208Cooled CANDLE Burning Reactors toward Practical Application for Future Nuclear Energy Source[J].Progress in Nuclear Energy 53(2011)886-890.
• [7]J.Wallenius,et al.A low power fast reactor cooled by natural circulation of LBE[R].Proceedings of Global2009,Paris,France,September 6-11,2009.
• [8]C.Rubbia,et al.Conceptual Design of a Fast Neutron Operated High Power Energy Amplier[R].CERN/AT/95-44(et),(1995).
• [9]Luciano Cinotti,et al.The Pb-Bi cooled XADS status of development[J].Journal of Nuclear Materials 301,2002:8-14.
• [10]HamidAIT Abderrahim,et al.MYRRHA:A European Experimental ADS for R&D Applications Status at Mid-2005 and Prospective towards Implementation[J].Journal of Nuclear Science and Technology,2007,44:491-498.
• [11]Y.Kurata,et al.The accelerator driven system strategy in Japan[J].Journal of Nuclear Materials 301,2002:1-7.
• [12]WonS.Park,et.al.HYPER(Hybrid Power Extraction Reactor):A system for clean nuclear energy[J].Nuclear Engineering and Design 199,2000:155-165.
• [13]C.Fazio,et al.Handbook on Lead-bismuth Eutectic Alloy and Lead Properties[R].Materials Compatibility,Thermalhydraulics and Technologies.2007 Edition.Nuclear Science.
• [14]Magdi Ragheb[R].Nuclear Marine Propulsion.2010.
• [15]Yuji Kurata,et al.Corrosion behavior of steels in liquid lead-bismuth with low oxygen concentrations[J].Journal of Nuclear Materials 2008,373:164-178.
• [16]Ning Li,Lead-alloy coolant technology and materialstechnology readiness level evaluation[J].Journal of Progress in Nuclear Energy 2008,50:140-150.
• [17]A.V.Zrodnikov et al.Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100[J].Journal of Nuclear Engineering and Design,2006,236:1490-1502.
• [18]Turbine contract for heavy metal SMR[N].World Nuclear News,2013.
• [19]Fast moves for nuclear development in Siberia[N].World Nuclear News,2012.
• [20]V.S.Smimov.Lead-Cooled Fast Reactor BRESTProject Status and Prospects[R].International Workshop on Innovative Nuclear Reactors Cooled by Heavy liquid metals:Status and Perspectives,Pisa,April 17-20,2012.
• [21]Alessandro Alemberti.The ALFRED project on Leadcooled Fast Reactor[R].ESNII Conference:Advanced fission research in Horizon 2020,June 25,2012.
• [22]ELFR The European Lead Fast Reactor:Design,Safety Approach And Safety Characteristics,Technical Meeting On”“Impact Of Fukushima Event On Current And Future Fast Reactor Designs”[R].HelmholtzZentrum Dresden-Rossendorf,Dresden,Germany,March 19-23,2012.
• [23]D.C.Wade,et al,STAR-H2:The Secure Transportable Autonomous Reactor For Hydrogen Producyion and Desalinization[R].ICONE10-22663(April 14-18 2002).
• [24]吴宜灿,等,大型集成多功能中子学计算与分析系统VisualBUS的研究与发展[J].核科学与工程,2007,27(4):365-373.