Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Acceleration method of fission source convergence based on RMC code

  • Pan, Qingquan (Department of Engineering Physics Tsinghua University) ;
  • Wang, Kan (Department of Engineering Physics Tsinghua University)
  • Received : 2019.07.29
  • Accepted : 2019.12.09
  • Published : 2020.07.25
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Abstract

To improve the efficiency of MC criticality calculation, an acceleration method of fission source convergence which gives an improved initial fission source is proposed. In this method, the MC global homogenization is carried out to obtain the macroscopic cross section of each material mesh, and then the nonlinear iterative solution of the SP3 equations is used to determine the fission source distribution. The calculated fission source is very close to the real fission source, which describes its space and energy distribution. This method is an automatic computation process and is tested by the C5G7 benchmark, the results show that this acceleration method is helpful to reduce the inactive cycles and overall running time.

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References

  1. S.S. Gorodkov, Using core symmetry in Monte Carlo dominance ratio calculations, Nucl. Sci. Eng. 168 (3) (2011) 242-247. https://doi.org/10.13182/NSE10-37
  2. M.J. Lee, H.G. Joo, D. Lee, K. Smith, Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation, Ann. Nucl. Energy 65 (2014) 101-113. https://doi.org/10.1016/j.anucene.2013.10.025
  3. J. Leppanen, Acceleration of fission source convergence in the Serpent 2 Monte Carlo code using a response matrix based solution for the initial source distribution, Ann. Nucl. Energy 128 (2019) 63-68. https://doi.org/10.1016/j.anucene.2018.12.044
  4. D.B. Elliott, et al., Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems, Ann. Nucl. Energy 119 (2018) 7-22. https://doi.org/10.1016/j.anucene.2018.04.039
  5. D. She, K. Wang, G.L. Yu, Asymptotic Wielandt method and superhistory method for source convergence in Monte Carlo criticality calculation, Nucl. Sci. Eng. 172 (2) (2012) 127-137. https://doi.org/10.13182/NSE11-44
  6. Q. Pan, J. Rao, K. Wang, Y. Zhou, Optimal source bias method based on RMC code, Ann. Nucl. Energy 121 (2018) 525-530. https://doi.org/10.1016/j.anucene.2018.08.026
  7. I. Mickus, J. Dufek, Optimal neutron population growth in accelerated Monte Carlo criticality calculations, Ann. Nucl. Energy 117 (2018) 297-304. https://doi.org/10.1016/j.anucene.2018.03.046
  8. Y. Chao, A new and rigorous SPN theory - part II: generalization to GSP(N), Ann. Nucl. Energy 110 (2017) 1176-1196. https://doi.org/10.1016/j.anucene.2017.08.020
  9. Y. Chao, A new and rigorous SPN theory - part III: a succinct summary of the GSPN theory, the P-3 equivalent GSP(3) and implementation issues, Ann. Nucl. Energy 119 (2018) 310-321. https://doi.org/10.1016/j.anucene.2018.04.029
  10. Q. Pan, K. Wang, An adaptive variance reduction algorithm based on RMC code for solving deep penetration problems, Ann. Nucl. Energy 128 (2019) 171-180. https://doi.org/10.1016/j.anucene.2019.01.009
  11. Q. Pan, H. Lu, D. Li, K. Wang, A new nonlinear iterative method for SPN theory, Ann. Nucl. Energy 110 (2017) 920-927. https://doi.org/10.1016/j.anucene.2017.07.030
  12. K. Wang, Z. Li, et al., Rmc - a Monte Carlo code for reactor core analysis, Ann. Nucl. Energy 82 (2015) 121-129. https://doi.org/10.1016/j.anucene.2014.08.048
  13. Q. Pan, K. Wang, One-step Monte Carlo global homogenization based on RMC code, Nucl. Eng. Technol. 51 (5) (2019) 1209-1217. https://doi.org/10.1016/j.net.2019.04.001
  14. M.A. Smith, E.E. Lewis, B.C. Na, Benchmark on deterministic transport calculations without spatial homogenization -a 2d/3d MOX fuel assembly benchmark, Tech. Rep. 16 (2003). NEA/NSC/DOC OECD/NEA.
  15. I. Petrovic, P. Benoist, BN Theory: Advances and New Models for Neutron Leakage Calculation, Plenum Press, New York, 1996, pp. 223-281.
  16. T. Hideki, M. Yasushi, Accuracy of interpolation methods for resonance self-shielding factors, Nucl. Sci. Technol. 18 (2) (1981) 152-161. https://doi.org/10.1080/18811248.1981.9733236
  17. J. Duderstadt, L. Hamilton, Nuclear Reactor Analysis, John wiley & Sons, Inc, New York, 1976.
  18. Z. Li, Development of Reactor Monte Carlo Code RMC and Research on Related Key Fundamental Methods [D], Tsinghua University, Beijing, 2012.
  19. L. Yu, In-depth Investigation and Further Development of Homogenization Method and Discontinuity Factor Theory [D], Shanghai Jiao Tong University, Shanghai, 2014.
  20. K.S. Smith, Spatial Homogenization Methods for Light Water Reactor, 1980. PhD thesis in Massachusetts Institute of Technology.

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