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Volume 32 Issue 2
Mar.  2025
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LIU Qingjie, WU Hongchun, CAO Liangzhi. Solution of Multiplying Binary Stochastic Neutron Transport Equation in One Dimensional Spherical Geometry[J]. Nuclear Power Engineering, 2011, 32(2): 6-11.
Citation: LIU Qingjie, WU Hongchun, CAO Liangzhi. Solution of Multiplying Binary Stochastic Neutron Transport Equation in One Dimensional Spherical Geometry[J]. Nuclear Power Engineering, 2011, 32(2): 6-11.

Solution of Multiplying Binary Stochastic Neutron Transport Equation in One Dimensional Spherical Geometry

  • Received Date: 2009-10-23
    Available Online: 2025-03-08
  • A statistical transport equation is presented in this paper to obtain the ensemble average keff for the binary stochastic media with random fissile pellets.Combined method of statistics and deterministics is proposed to directly solve the multiplying binary stochastic problem in 1-D spherical geometry.In the combined method,Monte Carlo sampling method is employed to determine the mean chord length of the stochastic system then deterministic SN diamond difference,source iteration method is used to solve the statistical transport equation with eigenvalue.Test stochastic problems of different scattering ratio,different chord-path ratio and different number of random fissile spheres are constructed and compared with references and uniformly-distributed approximated cases.Results show that the mean value of keff for the given systems can be predicted accurately by the statistical equation in most given cases.

     

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      沈阳化工大学材料科学与工程学院 沈阳 110142

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