Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations

  • Jiahao Chen (North Carolina State University, Department of Nuclear Engineering) ;
  • Jason Hou (North Carolina State University, Department of Nuclear Engineering) ;
  • Kostadin Ivanov (North Carolina State University, Department of Nuclear Engineering)
  • Received : 2022.11.12
  • Accepted : 2022.12.17
  • Published : 2023.04.25
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Abstract

A novel Fission Diffusion Synthetic Acceleration (FDSA) method is developed and implemented as a part of a hybrid neutronics method for source convergence acceleration and variance reduction in Monte Carlo (MC) criticality calculations. The acceleration of the MC calculation stems from constructing a synthetic operator and solving a low-order problem using information obtained from previous MC calculations. By applying the P1 approximation, two correction terms, one for the scalar flux and the other for the current, can be solved in the low-order problem and applied to the transport solution. A variety of one-dimensional (1-D) and two-dimensional (2-D) numerical tests are constructed to demonstrate the performance of FDSA in comparison with the standalone MC method and the coupled MC and Coarse Mesh Finite Difference (MC-CMFD) method on both intended purposes. The comparison results show that the acceleration by a factor of 3-10 can be expected for source convergence and the reduction in MC variance is comparable to CMFD in both slab and full core geometries, although the effectiveness of such hybrid methods is limited to systems with small dominance ratios.

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References

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