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Volume 31 Issue S2
Dec.  2010
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LI Yun-zhao, WU Hong-chun, CAO Liang-zhi, YAO Dong. Nodal SP3 Method for Solving Neutron Transport Equation[J]. Nuclear Power Engineering, 2010, 31(S2): 73-78,91.
Citation: LI Yun-zhao, WU Hong-chun, CAO Liang-zhi, YAO Dong. Nodal SP3 Method for Solving Neutron Transport Equation[J]. Nuclear Power Engineering, 2010, 31(S2): 73-78,91.

Nodal SP3 Method for Solving Neutron Transport Equation

  • Received Date: 2010-09-20
  • Rev Recd Date: 2010-10-25
  • Available Online: 2025-07-31
  • This paper establishes a nodal method to solve the two coupled equations transformed from the transport equation by SP3 method.In the nodal method,diffusion equation is discretized into average fluxes in the nodes and partial currents on the nodal boundaries.Nodal response relationship is obtained by expanding the detailed nodal flux into a sum of exponential functions.Numerical results demonstrates that the nodal SP3 method can treat polygonal meshes in different shapes with good parallel property,and that it can provide a similar accuracy while runs about six times faster than the nodal-SNN=4) method DNTR under the same mesh.

     

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