次临界能源堆物理设计进展
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摘要
聚变-裂变混合能源堆包括聚变中子源和次临界能源堆,主要目标是生产电能。回顾了国内外混合堆的发展历史,给出混合能源堆设计的边界条件和约束条件,说明次临界能源堆以铀锆合金为燃料、水为冷却剂的设计思想。利用输运燃耗耦合程序MCORGS计算了混合能源的燃耗,给出了中子有效增殖因数、能量放大倍数和氚增殖比等物理量随时间的变化。通过分析能谱和重要核素随燃耗时间的变化,说明混合能源堆与核燃料增殖、核废料嬗变混合堆的不同特点。论述了混合堆的热工设计并进行了安全分析。对于燃耗数值模拟程序,通过多家对算,保证其计算结果的可信性。针对次临界能源堆的特点,利用贫铀球壳建立了贫铀聚乙烯装置和贫铀LiH装置,并且专门设计加工了天然铀装置,开展铀裂变率、造钚率、产氚率等中子学积分实验,验证了数值模拟的可靠性。
In this paper,we propose a preliminary design for a fusion-fission hybrid energy reactor(FFHER),based on current fusion science and technology and well-developed fission technology.Design rules are listed and a primary concept blanket with uranium alloy as fuel and water as coolant is put forward.The uranium fuel can be natural uranium,LWR spent fuel,or depleted uranium.The FFHER design can increase the utilization rate of uranium in a comparatively simple way to sustain the development of nuclear energy.The interaction between the fusion neutron and the uranium fuel with the aim of achieving greater energy multiplication and tritium sustainability is studied.Other concept hybrid reactor designs are also reviewed.Integral neutron experiments were carried out to verify the credibility of our proposed physical design.The combination of the physical design with the related thermal hydraulic design,alloy fuel manufacture,and nuclear fuel cycle programs provides the science and technology basis for future development of the FFHER concept in China.
In this paper,we propose a preliminary design for a fusion-fission hybrid energy reactor(FFHER),based on current fusion science and technology and well-developed fission technology.Design rules are listed and a primary concept blanket with uranium alloy as fuel and water as coolant is put forward.The uranium fuel can be natural uranium,LWR spent fuel,or depleted uranium.The FFHER design can increase the utilization rate of uranium in a comparatively simple way to sustain the development of nuclear energy.The interaction between the fusion neutron and the uranium fuel with the aim of achieving greater energy multiplication and tritium sustainability is studied.Other concept hybrid reactor designs are also reviewed.Integral neutron experiments were carried out to verify the credibility of our proposed physical design.The combination of the physical design with the related thermal hydraulic design,alloy fuel manufacture,and nuclear fuel cycle programs provides the science and technology basis for future development of the FFHER concept in China.
引文
[1]彭先觉,师学明.核能与聚变裂变混合能源堆[J].物理,2010,39(6):385-389.(Peng Xianjue,Shi Xueming.Nuclear energy and fusion-fission hybrid reactor for pure energy production.Physics,2010,39(6):385-389)
[2]Li Maosheng,Liu Rong,Shi Xueming,et al.Preliminary design of hybrid energy reactor and integral neutron experiments[J].Fusion Engineering and Design,2012,87(7/8):1420-1424.
[3]Stacey W M.Transmutation missions for fusion neutron sources[J].Fusion Engineering and Design,2007,82:11-20.
[4]Cipiti B B,Cleary V D.Fusion transmutation of waste:design and analysis of the In-Zinerator concept[R].SAND2006-6590,2006.
[5]Powers J.Preliminary neutronics design studies for a molten salt blanket LIFE engine[R].LLNL-TR-408454,2008.
[6]Matsunaka M,Shido S,Burnup calculation of fusion-fission hybrid energy system with thorium cycle[J].Fusion Engineering and Design,2007,82:2779-2785.
[7]Murata I,Yamamoto Y,Shido S,et al.Fusion-driven hybrid system with ITER model[J].Fusion Engineering and Design,2005,75/79:871-875.
[8]Acir A.Effect of nuclear data libraries on tritium breeding in a(D-T)fusion driven reactor[J].J Fusion Energ,2008,27:301-307.
[9]师学明,张本爱.输运与燃耗耦合程序MCORGS的开发[J].核动力工程,2010,31(3):1-4.(Shi Xueming,Zhang Benai.Development of transport-burnup code MCPRGS.Nuclear Power Engineering,2010,31(3):1-4)
[10]Los Alamos National Laboratory.MCNP-A general Monte Carlo N-particle transport code[R].LA-UR-03-1987,2003.
[11]ORIGEN-S:Scale system module to calculate fuel depletion,actinide transmutation,fission product buildup and decay,and associated radiation source terms[R].NUREG/CR-200,2004.
[12]Powers J.Preliminary neutronics design studies for a molten salt blanket LIFE engine[R].LLNL-TR-408454,2008.
[13]Croff A G.ORIGEN2:A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials[J].Nuclear Technology,1983,62:335-352.
[14]Furuta K,Oka Y,Kondo S.CCC2464/BISON1.5,RSIC[R].Oak Ridge National Laboratory,1987.
[15]Bowman S M,Hollenbach D F,Dehart M D,et al.SCALE5:Powerful new criticality safety analysis tools[C]//The 7th International Conference on Nuclear Criticality Safety.2003.
[16]Furata K,Oak Y,Kondo S.CCC2464,RSIC computer code dollection[R].Oak Ridge National Laboratory,1987.
[17]邓梅根,冯开明.球形托卡马克堆嬗变中子学计算的比较研究[J].核聚变与等离子体物理,2003,23(1):7-12.(Deng Meigen,Feng Kaiming.Comparison study of transmutation neutronics calculation for a spherical Tokamak.Nuclear Fusion and Plasma Physics,2003,23(1):7-12)
[18]Cetnar J,Gronek P.BISON-C:A one dimensional transport and burnup calculation code with consideration of actinides and fission products[J].Nuclear Science and Engineering,2000,134:236-237.
[19]蒋校丰,谢仲生.蒙卡-燃耗程序系统及ADS基准题的计算[J].核科学与工程,2003,23(4):325-331.(Jiang Xiaofeng,Xie Zhongsheng.Monte Carlo-burnup code system and it’s application to IAEA ADS benchmark.Chinese Journal of Nuclear Science and Engineering,2003,23(4):325-331)
[20]李静惊,陈明亮,郑善良,等.基于离散纵标输运计算方法的三维燃耗程序发展研究[J].核科学与工程,2007,27(4):379-384.(Li Jingjing,Chen Mingliang,Zheng Shanliang,et al.Development of three-dimensional burnup code system based on discrete ordinates(SN)transport method.Chinese Journal of Nuclear Science and Engineering,2007,27(4):379-384)
[21]吴宜灿,李静惊,李莹,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.(Wu Yican,Li Jingjing,Li Ying,et al.An integrated multi-functional neutronics calculation and analysis code system:VisualBUS.Chinese Journal of Nuclear Science and Engineering,2007,27(4):365-373)
[22]余纲林,王侃,王煜宏.MCBurn—MCNP和ORIGEN耦合程序系统[J].原子能科学技术,2003,37(3):250-254.(Yu Ganglin,Wang Kan,Wang Yuhong.MCBurn—A coupling package of program MCNP and ORIGEN.Atomic Energy Science and Technology,2003,37(3):250-254)
[23]李浩泉.加速器驱动系统的中子物理学分析[D].北京:清华大学,2003.(Li Haoquan.Neutronics analysis on accelerator driven system.Beijing:Tsinghua University,2003)
[24]韩嵩,杨永伟.加速器驱动的次临界系统快堆次锕系核素非均匀布置堆芯的中子学研究[J].原子能科学技术,2006,40(6):718-722.(Han Song,Yang Yongwei.Neutronics study on minor actinide heterogeneous core of ADS fast reactor.AtomicEnergyScienceandTechnology,2006,40(6):718-722)
[25]徐红,杨永伟,周志伟.聚变-裂变混合堆水冷包层中子物理性能研究[J].原子能科学技术,2009,43(s):97-102.(Xu Hong,Yang Yongwei,Zhou Zhiwei.Neutron physical characteristics of light water cooled blanket of fusion-fission hybrid reactor.Atomic Energy Science and Technology,2009,43(s):97-102)
[26]邵增,程和平,梁志.聚变-裂变混合堆程序开发及验证[J].原子能科学技术,2009,43(s):244-247.(Shao Zeng,Cheng Heping,Liang Zhi.Development and validation for fusion-fission hybrid reactor codes.Atomic Energy Science and Technology,2009,43(s):244-247)
[27]师学明,彭先觉.混合能源堆包层中子学初步概念设计[J].核动力工程,2010,31(4):5-8.(Shi Xueming,Peng Xianjue.Preliminary concept design on blanket neutronics of a fusion-fission hybrid reactor for energy production.Nuclear Power Engineering,2010,31(4):5-8)
[28]李茂生,师学明,伊炜伟.聚变-裂变混合能源堆一维计算模型燃耗分析[J].原子能科学技术,2012,46(12):1440-1445.(Li Maosheng,Shi Xueming,Yi Weiwei.1DBurnup calculation of fusion-fission hybrid energy reactor.Atomic Energy Science and Technology,2012,46(12):1440-1445)
[29]Liu Rong,Zhu Tonghua,Yan Xiaosong,et al.Reaction rates in blanket assemblies of a fusion-fission hybrid reactor[J].Nuclear Science and Techniques,2012,23:242-246.
[30]严小松,刘荣,鹿心鑫,等.贫化铀/聚乙烯球壳交替系统中铀-238中子俘获率的测量与分析[J].物理学报,2012,61:102801.(Yan Xiaosong,Liu Rong,Lu Xinxin,et al.Measurement and analysis of neutron capture rate of U-238in an alternate depleted uranium/polyethylene system.Acta Physica Sinica,2012,61:102801)
[31]鹿心鑫,朱通华,刘荣,等.14MeV中子在贫化铀球中的造钚率的实验数据模拟分析[J].原子能科学技术,2011,45(6):645-650.(Lu Xinxin,Zhu Tonghua,Liu Rong,et al.Simulation and analysis of experimental plutonium production rates in depleted uranium sphere bombarded by 14MeV neutron.Atomic Energy Science and Technology,2011,45(6):645-650)
[32]王新华,郑普,刘荣,等.贫化铀、贫化铀/氢化锂组合装置的泄露中子能谱测量[J].核技术,2011,10:750-753.(Wang Xinhua,Zheng Pu,Liu Rong,et al.Measurement of leakage neutron spectra from spherical assemblies of DU and DU/LiH with 14MeV neutrons.2011,10:750-753)
[33]羊奕伟,严小松,刘荣,等.贫化铀球壳D-T中子诱发的铀反应率的测量与分析[J].物理学报,2013,62:022801.(Yang Yiwei,Yan Xiaosong,Liu Rong,et al.Measurements and analyses of uranium reaction rates on a depleted uranium shell with D-T neurtons.Acta Physica Sinica,2013,62:022801)
[2]Li Maosheng,Liu Rong,Shi Xueming,et al.Preliminary design of hybrid energy reactor and integral neutron experiments[J].Fusion Engineering and Design,2012,87(7/8):1420-1424.
[3]Stacey W M.Transmutation missions for fusion neutron sources[J].Fusion Engineering and Design,2007,82:11-20.
[4]Cipiti B B,Cleary V D.Fusion transmutation of waste:design and analysis of the In-Zinerator concept[R].SAND2006-6590,2006.
[5]Powers J.Preliminary neutronics design studies for a molten salt blanket LIFE engine[R].LLNL-TR-408454,2008.
[6]Matsunaka M,Shido S,Burnup calculation of fusion-fission hybrid energy system with thorium cycle[J].Fusion Engineering and Design,2007,82:2779-2785.
[7]Murata I,Yamamoto Y,Shido S,et al.Fusion-driven hybrid system with ITER model[J].Fusion Engineering and Design,2005,75/79:871-875.
[8]Acir A.Effect of nuclear data libraries on tritium breeding in a(D-T)fusion driven reactor[J].J Fusion Energ,2008,27:301-307.
[9]师学明,张本爱.输运与燃耗耦合程序MCORGS的开发[J].核动力工程,2010,31(3):1-4.(Shi Xueming,Zhang Benai.Development of transport-burnup code MCPRGS.Nuclear Power Engineering,2010,31(3):1-4)
[10]Los Alamos National Laboratory.MCNP-A general Monte Carlo N-particle transport code[R].LA-UR-03-1987,2003.
[11]ORIGEN-S:Scale system module to calculate fuel depletion,actinide transmutation,fission product buildup and decay,and associated radiation source terms[R].NUREG/CR-200,2004.
[12]Powers J.Preliminary neutronics design studies for a molten salt blanket LIFE engine[R].LLNL-TR-408454,2008.
[13]Croff A G.ORIGEN2:A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials[J].Nuclear Technology,1983,62:335-352.
[14]Furuta K,Oka Y,Kondo S.CCC2464/BISON1.5,RSIC[R].Oak Ridge National Laboratory,1987.
[15]Bowman S M,Hollenbach D F,Dehart M D,et al.SCALE5:Powerful new criticality safety analysis tools[C]//The 7th International Conference on Nuclear Criticality Safety.2003.
[16]Furata K,Oak Y,Kondo S.CCC2464,RSIC computer code dollection[R].Oak Ridge National Laboratory,1987.
[17]邓梅根,冯开明.球形托卡马克堆嬗变中子学计算的比较研究[J].核聚变与等离子体物理,2003,23(1):7-12.(Deng Meigen,Feng Kaiming.Comparison study of transmutation neutronics calculation for a spherical Tokamak.Nuclear Fusion and Plasma Physics,2003,23(1):7-12)
[18]Cetnar J,Gronek P.BISON-C:A one dimensional transport and burnup calculation code with consideration of actinides and fission products[J].Nuclear Science and Engineering,2000,134:236-237.
[19]蒋校丰,谢仲生.蒙卡-燃耗程序系统及ADS基准题的计算[J].核科学与工程,2003,23(4):325-331.(Jiang Xiaofeng,Xie Zhongsheng.Monte Carlo-burnup code system and it’s application to IAEA ADS benchmark.Chinese Journal of Nuclear Science and Engineering,2003,23(4):325-331)
[20]李静惊,陈明亮,郑善良,等.基于离散纵标输运计算方法的三维燃耗程序发展研究[J].核科学与工程,2007,27(4):379-384.(Li Jingjing,Chen Mingliang,Zheng Shanliang,et al.Development of three-dimensional burnup code system based on discrete ordinates(SN)transport method.Chinese Journal of Nuclear Science and Engineering,2007,27(4):379-384)
[21]吴宜灿,李静惊,李莹,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.(Wu Yican,Li Jingjing,Li Ying,et al.An integrated multi-functional neutronics calculation and analysis code system:VisualBUS.Chinese Journal of Nuclear Science and Engineering,2007,27(4):365-373)
[22]余纲林,王侃,王煜宏.MCBurn—MCNP和ORIGEN耦合程序系统[J].原子能科学技术,2003,37(3):250-254.(Yu Ganglin,Wang Kan,Wang Yuhong.MCBurn—A coupling package of program MCNP and ORIGEN.Atomic Energy Science and Technology,2003,37(3):250-254)
[23]李浩泉.加速器驱动系统的中子物理学分析[D].北京:清华大学,2003.(Li Haoquan.Neutronics analysis on accelerator driven system.Beijing:Tsinghua University,2003)
[24]韩嵩,杨永伟.加速器驱动的次临界系统快堆次锕系核素非均匀布置堆芯的中子学研究[J].原子能科学技术,2006,40(6):718-722.(Han Song,Yang Yongwei.Neutronics study on minor actinide heterogeneous core of ADS fast reactor.AtomicEnergyScienceandTechnology,2006,40(6):718-722)
[25]徐红,杨永伟,周志伟.聚变-裂变混合堆水冷包层中子物理性能研究[J].原子能科学技术,2009,43(s):97-102.(Xu Hong,Yang Yongwei,Zhou Zhiwei.Neutron physical characteristics of light water cooled blanket of fusion-fission hybrid reactor.Atomic Energy Science and Technology,2009,43(s):97-102)
[26]邵增,程和平,梁志.聚变-裂变混合堆程序开发及验证[J].原子能科学技术,2009,43(s):244-247.(Shao Zeng,Cheng Heping,Liang Zhi.Development and validation for fusion-fission hybrid reactor codes.Atomic Energy Science and Technology,2009,43(s):244-247)
[27]师学明,彭先觉.混合能源堆包层中子学初步概念设计[J].核动力工程,2010,31(4):5-8.(Shi Xueming,Peng Xianjue.Preliminary concept design on blanket neutronics of a fusion-fission hybrid reactor for energy production.Nuclear Power Engineering,2010,31(4):5-8)
[28]李茂生,师学明,伊炜伟.聚变-裂变混合能源堆一维计算模型燃耗分析[J].原子能科学技术,2012,46(12):1440-1445.(Li Maosheng,Shi Xueming,Yi Weiwei.1DBurnup calculation of fusion-fission hybrid energy reactor.Atomic Energy Science and Technology,2012,46(12):1440-1445)
[29]Liu Rong,Zhu Tonghua,Yan Xiaosong,et al.Reaction rates in blanket assemblies of a fusion-fission hybrid reactor[J].Nuclear Science and Techniques,2012,23:242-246.
[30]严小松,刘荣,鹿心鑫,等.贫化铀/聚乙烯球壳交替系统中铀-238中子俘获率的测量与分析[J].物理学报,2012,61:102801.(Yan Xiaosong,Liu Rong,Lu Xinxin,et al.Measurement and analysis of neutron capture rate of U-238in an alternate depleted uranium/polyethylene system.Acta Physica Sinica,2012,61:102801)
[31]鹿心鑫,朱通华,刘荣,等.14MeV中子在贫化铀球中的造钚率的实验数据模拟分析[J].原子能科学技术,2011,45(6):645-650.(Lu Xinxin,Zhu Tonghua,Liu Rong,et al.Simulation and analysis of experimental plutonium production rates in depleted uranium sphere bombarded by 14MeV neutron.Atomic Energy Science and Technology,2011,45(6):645-650)
[32]王新华,郑普,刘荣,等.贫化铀、贫化铀/氢化锂组合装置的泄露中子能谱测量[J].核技术,2011,10:750-753.(Wang Xinhua,Zheng Pu,Liu Rong,et al.Measurement of leakage neutron spectra from spherical assemblies of DU and DU/LiH with 14MeV neutrons.2011,10:750-753)
[33]羊奕伟,严小松,刘荣,等.贫化铀球壳D-T中子诱发的铀反应率的测量与分析[J].物理学报,2013,62:022801.(Yang Yiwei,Yan Xiaosong,Liu Rong,et al.Measurements and analyses of uranium reaction rates on a depleted uranium shell with D-T neurtons.Acta Physica Sinica,2013,62:022801)