西安脉冲堆燃耗对中子代时间的影响研究
|
摘要
本文研究了计算反应堆中子代时间(Λ)的瞬发中子通量密度衰减法,基于反应堆仅释放瞬发中子的假设条件,研究了瞬发中子动力学方程,将Λ的计算转变为α本征值的计算问题,采用MCNP程序模拟瞬发中子通量密度的衰减特性以拟合出α值。该方法避免了抽样计算中子价值函数的复杂问题,实现相对容易。并根据西安脉冲堆(XAPR)堆芯三维燃耗分布拟合出不同燃耗深度下瞬发中子通量密度衰减系数α,计算出堆芯中子代时间。结果表明:随着XAPR堆芯燃耗的加深,中子代时间呈增大趋势,从新堆芯到第一循环末(120EFPD),Λ增大幅度为8.93%。
The neutron generation time Λ is a very important reactor kinetics parameter. It is very significant for reactor operation and safety under reactor transient conditions. The prompt neutron flux density decay method is developed in the paper. Assuming that only prompt neutrons are produced in the reactor,the prompt kinetics equation is derived. And based on the prompt kinetics equation,the calculation of Λ is converted to α eigenvalue. Then the decay of prompt neutron flux density is simulated by the MCNP code to calculate α. The complicate problem calculating neutron importance function is avoided so that the method is easier to be achieved. According to the three-dimensional burnup distribution of the Xi'an pulsed reactor,the prompt neutron flux density attenuation coefficient is fitted and the Λ is calculated. The result indicates that the Λ is enlargement along with the increase of burnup. From the new core to 120 EFPD,the Λ increases by 8.93%.
The neutron generation time Λ is a very important reactor kinetics parameter. It is very significant for reactor operation and safety under reactor transient conditions. The prompt neutron flux density decay method is developed in the paper. Assuming that only prompt neutrons are produced in the reactor,the prompt kinetics equation is derived. And based on the prompt kinetics equation,the calculation of Λ is converted to α eigenvalue. Then the decay of prompt neutron flux density is simulated by the MCNP code to calculate α. The complicate problem calculating neutron importance function is avoided so that the method is easier to be achieved. According to the three-dimensional burnup distribution of the Xi'an pulsed reactor,the prompt neutron flux density attenuation coefficient is fitted and the Λ is calculated. The result indicates that the Λ is enlargement along with the increase of burnup. From the new core to 120 EFPD,the Λ increases by 8.93%.
引文
[1]Meulekamp R K,MARCK S C.Calculating the Effective Delayed Neutron Fraction Using Monte Carlo[J].Nuclear Science and Engineering,2006,152:142-148.
[2]NAUCHI Y,KAMEYAMA T.Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method[J].Journal of Nuclear Science And Technology,2010,47(11):977-990.
[3]VERBOOMEN B,HAECK W,BAETEN P.Monte Carlo calculation of the effective neutron generation time[J].Annals of Nuclear Energy,2006,33:911-916.
[4]Luka S,Andrej K,Gasper Z,et al.Monte Carlo calculation of kinetic parameters for the TRIGA MarkⅡresearch reactor[C].International Conference on Nuclear Energy for new Europe,2008.
[5]Bell G I,Glasstone S.Nuclear Reactor Theory[M].New York:Van Nostrand Reinhold Company,1970.
[6]谢仲生,吴宏春,张少泓.核反应堆物理分析(修订本)[M].西安:西安交通大学出版社,2004.
[7]Zhang L,Jiang XB,Zhang XY,et al.Monte Carlo Calculation of Neutron Generation Time in Critical and Subcritical Reactor with an External Source[C].Kyoto,PHYSOR,2014.
[8]杨岐,卜永熙,李达忠,等.西安脉冲反应堆[J].核动力工程,2002,23(6):1-7.DOI:0258-0926(2002)06-0001-07.Yang Qi,Pu Yongxi,Li Dazhong,et al.Xi’an Pulsed Reactor[J].Nuclear Power Engineering,2002,23(6):1-7.DOI:0258-0926(2002)06-0001-07.
[9]SNOJ L,KAV?I?A,?EROVNIK G,et al.Calculation of kinetic parameters for mixed TRIGA cores with Monte Carlo[J].Annals of Nuclear Energy,2010,37:223-229.
[10]张信一,赵柱民,江新标,等.基于MCNP与ORIGEN2耦合程序的IHNI-1型堆裂变产物中毒及燃耗分析[J].中国工程科学,2012,14(8):69-71.DOI:1009-1742(2012)08-0069-03.Zhang Xinyi,Zhao Zhumin,Jiang Xinbiao,et al.The fission product poisoning and burnup calculation for IHNI-1 reactor based on coupled code of MCNP-ORIGEN2[J].Engineering Sciences,2012,14(8):69-71.DOI:1009-1742(2012)08-0069-03.
[11]Committee on NS.International Handbook of Evaluated Criticality Safety Benchmark Experiments[R].NEA/NSC/DOC(95)03,2008.
[12]KIEDROWSKIA B C,BROWN F.Adjoint weighted kinetics parameters with continuous energy Monte Carlo[J].Trans Am Nucl Soc,2009,100:297-299.
[13]HANSEN G E.Status of Computational and Experimental Correlation of Los Alamos Fast Neutron Critical Assemblies[M].Proc.of Seminar on Physics of Fast and Intermediate Reactors.IAEA,Vienna,1962.
[2]NAUCHI Y,KAMEYAMA T.Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method[J].Journal of Nuclear Science And Technology,2010,47(11):977-990.
[3]VERBOOMEN B,HAECK W,BAETEN P.Monte Carlo calculation of the effective neutron generation time[J].Annals of Nuclear Energy,2006,33:911-916.
[4]Luka S,Andrej K,Gasper Z,et al.Monte Carlo calculation of kinetic parameters for the TRIGA MarkⅡresearch reactor[C].International Conference on Nuclear Energy for new Europe,2008.
[5]Bell G I,Glasstone S.Nuclear Reactor Theory[M].New York:Van Nostrand Reinhold Company,1970.
[6]谢仲生,吴宏春,张少泓.核反应堆物理分析(修订本)[M].西安:西安交通大学出版社,2004.
[7]Zhang L,Jiang XB,Zhang XY,et al.Monte Carlo Calculation of Neutron Generation Time in Critical and Subcritical Reactor with an External Source[C].Kyoto,PHYSOR,2014.
[8]杨岐,卜永熙,李达忠,等.西安脉冲反应堆[J].核动力工程,2002,23(6):1-7.DOI:0258-0926(2002)06-0001-07.Yang Qi,Pu Yongxi,Li Dazhong,et al.Xi’an Pulsed Reactor[J].Nuclear Power Engineering,2002,23(6):1-7.DOI:0258-0926(2002)06-0001-07.
[9]SNOJ L,KAV?I?A,?EROVNIK G,et al.Calculation of kinetic parameters for mixed TRIGA cores with Monte Carlo[J].Annals of Nuclear Energy,2010,37:223-229.
[10]张信一,赵柱民,江新标,等.基于MCNP与ORIGEN2耦合程序的IHNI-1型堆裂变产物中毒及燃耗分析[J].中国工程科学,2012,14(8):69-71.DOI:1009-1742(2012)08-0069-03.Zhang Xinyi,Zhao Zhumin,Jiang Xinbiao,et al.The fission product poisoning and burnup calculation for IHNI-1 reactor based on coupled code of MCNP-ORIGEN2[J].Engineering Sciences,2012,14(8):69-71.DOI:1009-1742(2012)08-0069-03.
[11]Committee on NS.International Handbook of Evaluated Criticality Safety Benchmark Experiments[R].NEA/NSC/DOC(95)03,2008.
[12]KIEDROWSKIA B C,BROWN F.Adjoint weighted kinetics parameters with continuous energy Monte Carlo[J].Trans Am Nucl Soc,2009,100:297-299.
[13]HANSEN G E.Status of Computational and Experimental Correlation of Los Alamos Fast Neutron Critical Assemblies[M].Proc.of Seminar on Physics of Fast and Intermediate Reactors.IAEA,Vienna,1962.
© 2004-2018 中国地质图书馆版权所有 京ICP备05064691号 京公网安备11010802017129号 地址：北京市海淀区学院路29号 邮编：100083 电话：办公室：(+86 10)66554848；文献借阅、咨询服务、科技查新：66554700 |