中国铅基研究实验堆燃料选择分析
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- 英文论文题名：The selection analysis of nuclear fuel of China LEAd-based Research Reactor
- 论文作者：梅华平 ; 吴庆生 ; 韩骞 ; 陈建伟 ; 黄群英 ; FDS团队
- 英文论文作者：MEI Hua-ping ; WU Qing-sheng ; HAN Qian ; CHEN Jian-wei ; HUANG Qun-ying ; Key Laboratory of Neutronics and Radiation Safety ; Institute of Nuclear Energy Safety Technology ; Chinese Academy of Sciences
- 年：2015
- 作者机构：中国科学院核能安全技术研究所中国科学院中子输运理论与辐射安全重点实验室;
- 论文关键词：中国铅基研究实验堆 ; 燃料 ; 富集度 ; UO_2
- 英文论文关键词：China LEAd-based research reactor ; fuel ; enrichment ; UO_2
- 会议召开时间：2015-09-21
- 会议录名称：中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第6册（核化学与放射化学分卷、核化工分卷）
- 语种：中文
- 分类号：TL352
- 学会代码：EGVD
- 会议名称：中国核学会2015年学术年会
- 会议地点：中国四川绵阳
- 主办单位：中国核学会
- 学会名称：中国核学会
- 页数：8
- 文件大小：487k
- 原文格式：O
- 会议级别：全国
摘要
中国铅基研究实验堆CLEAR-I(China LEAd-based Research Reactor)被确定为中国科学院战略性先导科技专项"未来先进核裂变能-ADS嬗变系统"的主选堆型。本文通过归纳传统快堆燃料的基本性质、工程应用以及富集度分布特点,基于国内现有燃料制造能力,综合考虑燃料富集度与经济成本等因素,最终确定富集度为19.75%的UO_2作为CLEAR-I首炉燃料。考虑闭式燃料循环和核废料嬗变功能,CLEAR-I后期将使用MOX及含次锕系元素的燃料。另外,从实验灵活性、未来可升级、与示范堆和商业堆平滑衔接、周期换料的经济性、燃料低浓化和循环策略等角度对该方案进行了分析。
China LE Ad-based Reactor(CLEAR-I) is selected as the reference reactor for the ADS program,which is performed by Institute of Nuclear Energy Safety Technology,Chinese Academy of Sciences(INEST).This paper summarized the basic physical properties,engineering applications and enrichment features of fast reactor fuels.Considering the current fuel production capacity and manufacturing cost in domestic,19.75% UO_2 has been selected as the initial fuel of CLEAR-I.MOX fuel and Minor Actinides-containing fuel are considered as the subsequence fuel in the future.Rationality of the scheme has been analyzed on the basis of nuclear non-proliferation,experimental flexibility,extendibility,smooth transition to demonstration and commercial reactor,refueling economy and fuel cycle strategy.
China LE Ad-based Reactor(CLEAR-I) is selected as the reference reactor for the ADS program,which is performed by Institute of Nuclear Energy Safety Technology,Chinese Academy of Sciences(INEST).This paper summarized the basic physical properties,engineering applications and enrichment features of fast reactor fuels.Considering the current fuel production capacity and manufacturing cost in domestic,19.75% UO_2 has been selected as the initial fuel of CLEAR-I.MOX fuel and Minor Actinides-containing fuel are considered as the subsequence fuel in the future.Rationality of the scheme has been analyzed on the basis of nuclear non-proliferation,experimental flexibility,extendibility,smooth transition to demonstration and commercial reactor,refueling economy and fuel cycle strategy.
引文
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[37]Wu Yican,Huang Qunying,Zhu Zhiqiang,et al.R&D of Dragon Series Lithium Lead loops for Material and Blanket Technology Testing[J].Fusion Science and Technology,2012,62-1:272-275.
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[40]Wu Yican,Progress in Fusion-Driven Hybrid System Studies in China[J].Fusion Engineering and Design,2002,63-64:73-80.
[41]Zrodnikov Anatoly,Toshinsky Georgy,Komlev Oleg,et al.,fuel cycle for reactor SVBR-100,Journal of Materials Science and Engineering[J].2011(Bl):929-937.
[2]吴宜灿,黄群英,柏云清,等.液态铅铋回路设计研制与材料腐蚀实验初步研究.核科学与工程[J].2010,30(3):238-243.
[3]吴宜灿,柏云清,宋勇,等.中国铅基研究反应堆概念设计研究.核科学与工程[J].2014(2):201-208.
[4]柏云清,汪卫华,蒋洁琼,等.加速器驱动核废料嬗变堆CLEAR概念设计[C].第五届反应堆物理与核材料学术研讨会.2011.
[5]Mathias Hareland,Key issues to the lead-cooled fast reactor design[R].Uppsala Universitet,2011.
[6]T.R.Allen,D.C.Crawford,Lead-cooled fast reactor systems and the fuels and materials challenges[J].Science and Technology of Nuclear Installations,Hindawi,2007.
[7]Rogozkin,B.D.,Stepennova,N.V.,et al.,Mononitride U-Pu mixed fuel and its electrochemical reprocessing in molten salts[R].IAEA TECDOC 1348,IAEA,2003.
[8]易伟,代胜平,沈保罗,等.氮化铀粉末合成工艺研究[J].核动力工程,2007,28(5).
[9]李冠兴,武胜.核燃料[M].化学工业出版社,2007.
[10]IAEA,Fast reactor database 2006 update,IAEA-TECDOC-1531[R].IAEA,2006.
[11]H.Ait Abderrahim,V.Sobolev,E Malambu,Fuel design for the experimental ADS MYRRHA[R].Technical Meeting on use of LEU in ADS,Vienna,IAEA,2005.
[12]IAEA,Status of small reactor designs without on-site refuelling,IAEA-TECDOC-1536[R].IAEA,2007.
[13]Brian Cox,Friedrich Garzarolli,Ron Adamson,et al.,Fuel material technology report[R].Advanced Nuclear Technology International Krongjutarvagen,SKULTUNA,Sweden.2006.
[14]Craig F.Smith,William G.Halsey,Neil W.Brown,et al.SSTAR:The US lead-cooled fast reactor(LFR)[J].Journal of Nuclear Materials,2008,376:255-259.
[15]IAEA,Advanced fuel pellet materials and designs for water cooled reactors,IAEA-TECDOC-1416[R].IAEA,2004.
[16]Won Chang Nam,Hyong Won Lee,Il Soon Hwang,Fuel design study and optimization for PEACER development[J].Nuclear Engineering and Design,2007,237:316-324.
[17]Hiroshi Sekimoto,Mingyu Yan,Design study on small CANDLE reactor[J].Energy Conversion and Management,2008,49:1868-1872.
[18]Minoru Takahashi,Shoji Uchida,Yoshiyuki Kasahara,Design study on reactor structure of Pb-Bi-cooled direct contact boiling water fast reactor(PBWFR)[J].Progress in Nuclear Energy,2008,50:197-205.
[19]S.Bortot,A.Moisseytsev,J.J.Sienicki,et al.,Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator[J].Nuclear Engineering and Design,2011,241:3021-3031.
[20]Marco Colombo,Antonio Cammi,Vito Memoli,et al.,Transfer function modelling of the Lead-cooled Fast Reactor(LFR)dynamics[J].Progress in Nuclear Energy,2010,52:715-729.
[21]V.V.ORLOV,A.I.FILIN,A.V.LOPATKIN,et al.,The closed on-site fuel cycle of the BREST reactors[J].Progress in Nuclear Energy,2005,47(1-4):171-177.
[22]A.V.Zrodnikov,G.I.Toshinsky,O.G.Komlev,et al.,SVBR-100 module-type fast reactor of the IV generation for regional power industry[J].Journal of Nuclear Materials,2011,415:237-244.
[23]Craig F.Smith,William G.Halsey,Neil W.Brown,et al.,SSTAR:The US lead-cooled fast reactor(LFR)[J].Journal of Nuclear Materials,2008,376:255-259.
[24]SIENICKI,J.J.,MOISSEYTSEV,A.V.,SSTAR lead-cooled,small modular fast reactor for deployment at remote sites-system thermal hydraulic development[R].Int.Conf.on Advances in Nuclear Power Plants Seoul,ICAPP,2005.
[25]MOISSEYTSEV,A.,SIENICKI,J.J.,WADE,D.C.,Lead-to-CO_2 heat exchangers for coupling of the STAR-LM LFR to a supercritical carbon dioxide Brayton cycle power converter[R].12th Int.Conf.on Nuclear Engineering,ASME,2004.
[26]WADE,D,DOCTOR,R.,PEDDICORD,L.,STAR-H2:A battery-type lead cooled fast reactor for hydrogen manufacture in a sustainable hierarchical hub spoke energy infrastructure[R].Proc.Int.Conf.Kyoto,GENES4/ANP,2003.
[27]叶国安,中国核燃料循环后段现状与发展[C].第二届中法核燃料循环后段研讨,成都,中国原子能科学研究院,2013.09.
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[29]IAEA,Status and advances in MOX fuel technology[R].TECHNICAL REPORTS SERIES NO.415,IAEA,2003.
[30]Wu Yican,Chen Hongli,Huang Qunying,et al.Lead alloy cooled fast reactor development plan and R&D status in China[C].International Conference on Fast Reactor and Related Fuel Cycles:Safe Technologies and Sustainable Scenarios(FR13),Pairs,France,March 4-7,2013.
[31]Bai Yunqing,Conceptual design of lead-bismuth cooled accelerator driven subcritical reactor[R].Proceedings of5th Int.Conf.on Emerging Nuclear Energy Systems(ICENES-15),San Francisco,USA,May 15-19,2011.
[32]吴宜灿,黄群英,柏云清,等.液态铅铋回路设计研制与材料腐蚀实验初步研究[J].核科学与工程,2010,30(3):238-243.
[33]Wu Yican,Jiang Jieqiong,Yu Jie,The Fusion-Driven Hybrid System and Its Material Selection[J].Journal of Nuclear Materials,2002,307-311:1629-1636.
[34]Wu Yican,Jiang Jieqiong,Wang Ming,et al.A Fusion-Driven Subcritical System Concept Based on Viable Technologies[J].Nuclear Fusion,2011,51(10):103036.
[35]Wu Yican,FDS Team,Conceptual Design of the China Fusion Power Plant FDS-Ⅱ[J].Fusion Engineering and Design,2008,83(10-12):1683-1689.
[36]吴宜灿,黄群英,朱志强,等.中国系列液态锂铅实验回路设计与研发进展[J].核科学与工程,2009,9(2):161-169.
[37]Wu Yican,Huang Qunying,Zhu Zhiqiang,et al.R&D of Dragon Series Lithium Lead loops for Material and Blanket Technology Testing[J].Fusion Science and Technology,2012,62-1:272-275.
[38]Huang Qunying,Gao Sheng,Zhu Zhiqiang,et al.Progress in Compatibility Experiments on Lithium-Lead with Candidate Structural Materials for Fusion in China[J].Fusion Engineering and Design,2009,84:242-246.
[39]Wu Yican,Design Status and Development Strategy of China Liquid Lithium-Lead Blankets and Related Material Technology[J].Journal of Nuclear Materials,2007,367-370:1410-1415.
[40]Wu Yican,Progress in Fusion-Driven Hybrid System Studies in China[J].Fusion Engineering and Design,2002,63-64:73-80.
[41]Zrodnikov Anatoly,Toshinsky Georgy,Komlev Oleg,et al.,fuel cycle for reactor SVBR-100,Journal of Materials Science and Engineering[J].2011(Bl):929-937.
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