Calculation of neutron importance in Xi'an pulsed reactor

被引:0
作者
Zhang, Liang [1 ,2 ]
Jiang, Xin-Biao [1 ,2 ]
Chen, Li-Xin [1 ,2 ]
Yang, Ning [1 ,2 ]
Zhang, Xin-Yi [1 ,2 ]
机构
[1] Northwest Institute of Nuclear Technology, Xi'an
[2] State Key Laboratory of Simulation and Effect for Intense Pulse Radiation, Xi'an
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2015年 / 49卷
关键词
CITATION; Effective delayed neutron fraction; Neutron generation time; Neutron importance; WIMS;
D O I
10.7538/yzk.2015.49.S0.0063
中图分类号
学科分类号
摘要
The neutron importance, which is an important parameter of nuclear reactor, means the contribution of the neutron to the reactor power. The 6-group homogenized cross-section of Xi'an Pulsed Reactor was obtained with the cell calculation code WIMS. And the neutron importance distribution was achieved with the diffusion calculation code CITATION. The diffusion calculation was validated with continuous-energy Monte Carlo code MCNP. The space and energy distribution of neutron importance was analyzed. The effect of the neutron importance distribution on the kinetics parameters, namely, the effective delayed neutron fraction and the neutron generation time, were studied. The results show that the neutron importance decreases with the increasing of the neutron energy in the fuel cell. However, in the control rod cell and the central water cell, the neutron importance gets larger with the decreasing of the neutron energy. The reason that the effective delayed neutron fraction is larger than delayed neutron fraction is the importance of the delayed fission neutrons is greater than that of the prompt fission neutrons. And the reason that the neutron generation time is smaller than the prompt neutron lifetime is the neutron importance in the fuel cell is larger than that in the other cells. © 2015, Atomic Energy Press. All right reserved.
引用
收藏
页码:63 / 67
页数:4
相关论文
共 11 条
  • [1] Wigner E.P., The Collected Works of Eugene Paul Wigner: Effect of Small Perturbations on Pile Period, (1992)
  • [2] Henry A.F., Nuclear Reactor Analysis, (1975)
  • [3] Bell G.I., Glasstone S., Nuclear Reactor Theory, (1970)
  • [4] Feghhi S.A.H., Shahriari M., Afarideh H., Calculation of neutron importance function in fissionable assemblies using Monte Carlo method, Annals of Nuclear Energy, 34, pp. 514-520, (2007)
  • [5] Nauchi Y., Kameyama T., Proposal of direct calculation of kinetic parameters β<sub>eff</sub>and Λ based on continuous energy Monte Carlo method, Journal of Nuclear Science and Technology, 42, 6, pp. 503-514, (2005)
  • [6] Nauchi Y., Kameyama T., Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method, Journal of Nuclear Science and Technology, 47, 11, pp. 977-990, (2010)
  • [7] Meulekamp R.K., van der Marck S.C., Calculating the effective delayed neutron fraction using Monte Carlo, Nuclear Science and Engineering, 152, pp. 142-148, (2006)
  • [8] Kiedrowski B.C., Booth T.E., Brown F.B., Et al., MCNP5-1.60 feature enhancements & manual clarifications, (2010)
  • [9] Briesmeister J.F., Mont Carlo N-particle transport, (2000)
  • [10] OECD/NEA Nuclear Science Committee, International handbook of evaluated criticality safety benchmark experiments, (2008)