铅冷快堆M~2LFR-1000堆芯燃料管理方案设计
|
摘要
堆芯燃料管理是反应堆设计中极为重要而且复杂的工作,直接影响着堆芯的经济性。目前国内外对于压水堆等传统热堆已有了较为丰富和成熟的燃料管理计算方法,但对于快堆,由于其中子能谱硬,与传统热堆相比有着不同的控制方式和功率分布,快堆的堆芯燃料管理缺乏系统研究。针对中国科学技术大学自主研发的强迫循环冷却的铅基快堆M~2LFR-1000,应用SRAC/COREBN软件包进行堆芯燃耗计算,根据燃耗深度提取核素核子密度,计算伪平衡循环参数进行燃料管理预估,然后进行首循环装料、过渡循环和平衡循环燃料管理方案设计。结果表明:对M~2LFR-1000堆芯外区燃料换料组件Pu的富集度进行优化,可以延长换料周期到540d,提高平均卸料燃耗深度;伪平衡循环结果与平衡循环基本一致,伪平衡循环可以用于燃料管理预估。
Fuel management is an extremely important and complex work in reactor design and directly affects the economics of the reactor.Now,there are many mature fuel management calculation methods for PWR and other traditional thermal reactors around the world.However,because of their hard neutron spectra,control modes and power distributions of fast reactors are different from those of traditional thermal reactors.There is a lack of systematic study of fuel management for fast reactors.Based on the SRAC/COREBN software package which provides the atom density of the nuclides at different burnup levels,apseudo-equilibrium cycle parameter was calculated for the fuel management pre-estimation of forced circulation lead cooled fast reactor M~2LFR-1000 independently developed by University of Science and Technology of China.Then,refueling schemes of the initial,transition and equilibrium cycles were designed.The results show that optimizing the Pu enrichment of outer fuel assemblies in M~2LFR-1000 core can extend the cycle length to 540 dand increase the average discharge burnup.The pseudo-equilibrium cycle results are basically the same as those of the equilibrium cycle.The pseudo-equilibrium cycle can be used for fuel management preestimation.
Fuel management is an extremely important and complex work in reactor design and directly affects the economics of the reactor.Now,there are many mature fuel management calculation methods for PWR and other traditional thermal reactors around the world.However,because of their hard neutron spectra,control modes and power distributions of fast reactors are different from those of traditional thermal reactors.There is a lack of systematic study of fuel management for fast reactors.Based on the SRAC/COREBN software package which provides the atom density of the nuclides at different burnup levels,apseudo-equilibrium cycle parameter was calculated for the fuel management pre-estimation of forced circulation lead cooled fast reactor M~2LFR-1000 independently developed by University of Science and Technology of China.Then,refueling schemes of the initial,transition and equilibrium cycles were designed.The results show that optimizing the Pu enrichment of outer fuel assemblies in M~2LFR-1000 core can extend the cycle length to 540 dand increase the average discharge burnup.The pseudo-equilibrium cycle results are basically the same as those of the equilibrium cycle.The pseudo-equilibrium cycle can be used for fuel management preestimation.
引文
[1]Alemberti A,Carlsson J,Malambu E,et al.European lead fast reactor-ELSY[J].Nuclear Engineering&Design,2011,241(9):3470-3480.
[2]肖宏才.自然安全的BREST铅冷快堆——现代核能体系中最具发展潜力的堆型[J].核科学与工程,2015,35(3):395-406.(Xiao Hongcai.Lead-cooled natural safe fast reactor BREST—The most potential reactor in the modern nuclear power system.Nuclear Science and Engineering,2015,35(3):395-406)
[3]Chen H,Chen Z,Chen C,et al.Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100[J].International Journal of Hydrogen Energy,2016,41(17):7158-7168.
[4]Chen H,Zhang X,Zhao Y,et al.A medium-power modular lead-cooled fast reactor M2LFR-1000emphasizing application of optimization methods in preliminary design[C]//The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics(WORTH-8).2017.
[5]李友谊,杨晓强,姚进国,等.田湾核电站18个月换料燃料管理策略[J].原子能科学技术,2014,48(11):2072-2077.(Li Youyi,Yang Xiaoqiang,Yao Jinguo,et al.Fuel management scheme on 18months refueling for Tianwan nuclear power station.Atomic Energy Science and Technology,2014,48(11):2072-2077)
[6]姚红.157组燃料组件组成的堆芯燃料管理研究[J].原子能科学技术,2013,47(10):1845-1851.(Yao Hong.Fuel management study on PWR core included of 157fuel assemblies.Atomic Energy Science and Technology,2013,47(10):1845-1851)
[7]刘国明,郭治鹏.HPR1000堆芯装载50%MOX组件的燃料管理方案[J].强激光与粒子束,2017,29:036010.(Liu Guoming,Guo Zhipeng.Fuel loading pattern with 50%MOX fuel in HPR1000core.High Power Laser and Particle Beams,2017,29:036010)
[8]赵晶,刘志宏,郭德朋,等.大功率压水堆堆芯燃料管理设计[J].原子能科学技术,2012,46(s1):397-402.(Zhao Jing,Liu Zhihong,Guo Depeng,et al.In-core fuel management design of large power PWR.Atomic Energy Science and Technology,2012,46(s1):397-402)
[9]Castillo A,Ortiz J J,Montes J L,et al.Fuel loading and control rod patterns optimization in a BWR using Tabu search[J].Annals of Nuclear Energy,2007,34(3):207-212.
[10]Ortiz J J,Requena I.Using a multi-state recurrent neural network to optimize loading patterns in BWRs[J].Annals of Nuclear Energy,2004,31(7):789-803.
[11]Grasso G,Petrovich C,Mattioli D,et al.The core design of ALFRED,a demonstrator for the European lead-cooled reactors[J].Nuclear Engineering&Design,2014,278(278):287-301.
[12]Petrovich C,Grasso C,Rocchi F.D07-definition of the ETDR core and neutronic characterization—Part I[R].Italy:Centro Ricerche Bologna,2013.
[13]Petrovich C.ALFRED core.Summary,synoptic tables,conclusions and recommendations[R].Italy:Centro Ricerche Bologna,2013.
[14]杨晓燕.快堆堆芯燃料管理优化研究[D].北京:清华大学,2010.(Yang Xiaoyan.Research on optimization of in-core fuel management of fast reactor.Beijing:Tsinghua University,2010)
[15]Okumura K,Kugo T,Kaneko K,et al.SRAC2006:a comprehensive neutronics calculation code system[R].Japan Atomic Energy Agency,2007.
[16]Okumura K.COREBN:A core burn-up calculation module for SRAC2006[R].Japan Atomic Energy Agency,2007.
[17]X-5 Monte Carlo Team.MCNP-A general Monte Carlo N-particle transport code[R].Los Alamos National Laboratory,2003.
[18]吕征,沈峰,孙志勇,等.SRAC程序在中国先进研究堆上的应用研究[J].原子能科学技术,2009,43(s2):407-411.(LüZheng,Shen Feng,Sun Zhiyong,et al.Application of SRAC system on china advanced research reactor.Atomic Energy Science and Technology,2009,43(s2):407-411)
[2]肖宏才.自然安全的BREST铅冷快堆——现代核能体系中最具发展潜力的堆型[J].核科学与工程,2015,35(3):395-406.(Xiao Hongcai.Lead-cooled natural safe fast reactor BREST—The most potential reactor in the modern nuclear power system.Nuclear Science and Engineering,2015,35(3):395-406)
[3]Chen H,Chen Z,Chen C,et al.Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100[J].International Journal of Hydrogen Energy,2016,41(17):7158-7168.
[4]Chen H,Zhang X,Zhao Y,et al.A medium-power modular lead-cooled fast reactor M2LFR-1000emphasizing application of optimization methods in preliminary design[C]//The 8th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics(WORTH-8).2017.
[5]李友谊,杨晓强,姚进国,等.田湾核电站18个月换料燃料管理策略[J].原子能科学技术,2014,48(11):2072-2077.(Li Youyi,Yang Xiaoqiang,Yao Jinguo,et al.Fuel management scheme on 18months refueling for Tianwan nuclear power station.Atomic Energy Science and Technology,2014,48(11):2072-2077)
[6]姚红.157组燃料组件组成的堆芯燃料管理研究[J].原子能科学技术,2013,47(10):1845-1851.(Yao Hong.Fuel management study on PWR core included of 157fuel assemblies.Atomic Energy Science and Technology,2013,47(10):1845-1851)
[7]刘国明,郭治鹏.HPR1000堆芯装载50%MOX组件的燃料管理方案[J].强激光与粒子束,2017,29:036010.(Liu Guoming,Guo Zhipeng.Fuel loading pattern with 50%MOX fuel in HPR1000core.High Power Laser and Particle Beams,2017,29:036010)
[8]赵晶,刘志宏,郭德朋,等.大功率压水堆堆芯燃料管理设计[J].原子能科学技术,2012,46(s1):397-402.(Zhao Jing,Liu Zhihong,Guo Depeng,et al.In-core fuel management design of large power PWR.Atomic Energy Science and Technology,2012,46(s1):397-402)
[9]Castillo A,Ortiz J J,Montes J L,et al.Fuel loading and control rod patterns optimization in a BWR using Tabu search[J].Annals of Nuclear Energy,2007,34(3):207-212.
[10]Ortiz J J,Requena I.Using a multi-state recurrent neural network to optimize loading patterns in BWRs[J].Annals of Nuclear Energy,2004,31(7):789-803.
[11]Grasso G,Petrovich C,Mattioli D,et al.The core design of ALFRED,a demonstrator for the European lead-cooled reactors[J].Nuclear Engineering&Design,2014,278(278):287-301.
[12]Petrovich C,Grasso C,Rocchi F.D07-definition of the ETDR core and neutronic characterization—Part I[R].Italy:Centro Ricerche Bologna,2013.
[13]Petrovich C.ALFRED core.Summary,synoptic tables,conclusions and recommendations[R].Italy:Centro Ricerche Bologna,2013.
[14]杨晓燕.快堆堆芯燃料管理优化研究[D].北京:清华大学,2010.(Yang Xiaoyan.Research on optimization of in-core fuel management of fast reactor.Beijing:Tsinghua University,2010)
[15]Okumura K,Kugo T,Kaneko K,et al.SRAC2006:a comprehensive neutronics calculation code system[R].Japan Atomic Energy Agency,2007.
[16]Okumura K.COREBN:A core burn-up calculation module for SRAC2006[R].Japan Atomic Energy Agency,2007.
[17]X-5 Monte Carlo Team.MCNP-A general Monte Carlo N-particle transport code[R].Los Alamos National Laboratory,2003.
[18]吕征,沈峰,孙志勇,等.SRAC程序在中国先进研究堆上的应用研究[J].原子能科学技术,2009,43(s2):407-411.(LüZheng,Shen Feng,Sun Zhiyong,et al.Application of SRAC system on china advanced research reactor.Atomic Energy Science and Technology,2009,43(s2):407-411)