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Based on the research of the uniform fission site algorithm, the uniform tally density algorithm and the uniform track number density algorithm are proposed and compared with the original uniform fission site algorithm in this paper for seeking high performance of global tallying in Monte Carlo criticality calculation. Because reducing the largest uncertainties to an acceptable level simply by running a large number of neutron histories is often prohibitively expensive, the researches are indispensable for the calculation to reach the goal of practical application (the so called 95/95 standard). Using the global volume-averaged cell flux tally and energy deposition tally of the pin-by-pin model of Dayawan nuclear reactor as two examples, these new algorithms show better results. Although the uniform tally density algorithm has the best performance, the uniform track number density algorithm still has the advantage of being applicable to any type of tally, which is based on the track length estimator without any modification. All the algorithms are realized in a recently developed parallel Monte Carlo particle transport code JMCT.
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Keywords:
- Monte Carlo method /
- criticality calculation /
- global tally
[1] Li G, Deng L, Li S, Mo Z Y 2011 Acta Phys. Sin. 60 022401 (in Chinese) [李刚, 邓力, 李树, 莫则尧 2011 60 022401]
[2] Li S, Li G, Tian D F, Deng L 2013 Acta Phys. Sin. 62 249501 (in Chinese) [李树, 李刚, 田东风, 邓力 2013 62 249501]
[3] Brown F B 2009 Proceedings of International Conference of Mathematics, Computational Methods Reactor Physics Saratoga Springs, New York, USA, May 3-7, 2009
[4] Herman B R 2014 Ph. D. Dissertation (Cambridge: Massachusetts Institute of Technology)
[5] Smith K S 2011 Trans. Am. Nucl. Soc. 104 313
[6] Kelly D J, Sutton T M, Wilson S C 2012 Proceedings of PHYSOR 2012 Knoxville, Tennessee, USA, April 15-20, 2012
[7] Kelly D J, Aviles B N, Herman B R 2013 Proceedings of MC 2013 Sun Valley, Idaho, USA, May 5-9, 2013 p2962
[8] Hunter J L, Sutton T M 2013 Proceedings of MC 2013 Sun Valley, Idaho, USA, May 5-9, 2013 p2780
[9] Shangguan D H, Li G, Deng L, Zhang B Y, Li R, Fu Y G 2015 Acta. Phys. Sin. 64 052801 (in Chinese) [上官丹骅, 李刚, 邓力, 张宝印, 李瑞, 付元光 2015 64 052801]
[10] Zhang B Y, Li G, Deng L, Ma Y, Shangguan D H, Zhang A Q, Cao X L, Mo Z Y 2014 Proceedings of PHYSOR 2014 Kyoto, Japan, Sep. 28-Oct. 3, 2014
[11] Deng L, Ye T, Li G, Zhang B Y, Shangguan D H 2014 Proceedings of PHYSOR 2014 Kyoto, Japan, Sep. 28-Oct. 3, 2014
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[1] Li G, Deng L, Li S, Mo Z Y 2011 Acta Phys. Sin. 60 022401 (in Chinese) [李刚, 邓力, 李树, 莫则尧 2011 60 022401]
[2] Li S, Li G, Tian D F, Deng L 2013 Acta Phys. Sin. 62 249501 (in Chinese) [李树, 李刚, 田东风, 邓力 2013 62 249501]
[3] Brown F B 2009 Proceedings of International Conference of Mathematics, Computational Methods Reactor Physics Saratoga Springs, New York, USA, May 3-7, 2009
[4] Herman B R 2014 Ph. D. Dissertation (Cambridge: Massachusetts Institute of Technology)
[5] Smith K S 2011 Trans. Am. Nucl. Soc. 104 313
[6] Kelly D J, Sutton T M, Wilson S C 2012 Proceedings of PHYSOR 2012 Knoxville, Tennessee, USA, April 15-20, 2012
[7] Kelly D J, Aviles B N, Herman B R 2013 Proceedings of MC 2013 Sun Valley, Idaho, USA, May 5-9, 2013 p2962
[8] Hunter J L, Sutton T M 2013 Proceedings of MC 2013 Sun Valley, Idaho, USA, May 5-9, 2013 p2780
[9] Shangguan D H, Li G, Deng L, Zhang B Y, Li R, Fu Y G 2015 Acta. Phys. Sin. 64 052801 (in Chinese) [上官丹骅, 李刚, 邓力, 张宝印, 李瑞, 付元光 2015 64 052801]
[10] Zhang B Y, Li G, Deng L, Ma Y, Shangguan D H, Zhang A Q, Cao X L, Mo Z Y 2014 Proceedings of PHYSOR 2014 Kyoto, Japan, Sep. 28-Oct. 3, 2014
[11] Deng L, Ye T, Li G, Zhang B Y, Shangguan D H 2014 Proceedings of PHYSOR 2014 Kyoto, Japan, Sep. 28-Oct. 3, 2014
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