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ORIGINAL PAPER

Reliable Method for Fission Source Convergence of Monte Carlo Criticality Calculation with Wielandt's Method

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Pages 99-107 | Received 16 Sep 2003, Accepted 23 Nov 2003, Published online: 07 Feb 2012

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Qingquan Pan, Tengfei Zhang, Xiaojing Liu, Yun Cai, Lianjie Wang & Kan Wang. (2022) Optimal Batch Size Growth for Wielandt Method and Superhistory Method. Nuclear Science and Engineering 196:2, pages 183-192.
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Ding She, Kan Wang & Ganglin Yu. (2012) Asymptotic Wielandt Method and Superhistory Method for Source Convergence in Monte Carlo Criticality Calculation. Nuclear Science and Engineering 172:2, pages 127-137.
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Ze-Guang Li, Kan Wang, Yu-Chuan Guo & Xiao-Yu Guo. (2021) Forced propagation method for Monte Carlo fission source convergence acceleration in the RMC. Nuclear Science and Techniques 32:3.
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M.R. Omar, J.A. Karim & T.L. Yoon. (2020) An efficient Monte Carlo fission source convergence acceleration strategy adapted from the survival biasing technique. Annals of Nuclear Energy 138, pages 107164.
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Toshihiro Yamamoto & Hiroki Sakamoto. (2019) A Monte Carlo technique for sensitivity analysis of alpha-eigenvalue with the differential operator sampling method. Annals of Nuclear Energy 127, pages 178-187.
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Elliott D. Biondo, Gregory G. Davidson, Tara M. Pandya, Steven P. Hamilton & Thomas M. Evans. (2018) Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems. Annals of Nuclear Energy 119, pages 7-22.
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Wei Wei, Yi Wang, Ruihong Wang, Shulin Yang & Liujun Pan. (2018) Monte Carlo fission matrix acceleration method based on redistributing mesh. Monte Carlo fission matrix acceleration method based on redistributing mesh.
Ignas Mickus & Jan Dufek. (2018) Optimal neutron population growth in accelerated Monte Carlo criticality calculations. Annals of Nuclear Energy 117, pages 297-304.
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Davide Mancusi & Andrea Zoia. (2018) Chaos in eigenvalue search methods. Annals of Nuclear Energy 112, pages 354-363.
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Toshihiro Yamamoto. (2018) Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method. Annals of Nuclear Energy 112, pages 150-157.
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Brian C. Kiedrowski & Charles D. Corbin. (2017) Monte Carlo and deterministic calculation of the mutual information of the fission source in k-eigenvalue calculations. Progress in Nuclear Energy 101, pages 435-443.
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Sung Hoon Choi & Hyung Jin Shim. (2016) Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method. Annals of Nuclear Energy 96, pages 287-294.
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Jan Dufek & Kaur Tuttelberg. (2016) Monte Carlo criticality calculations accelerated by a growing neutron population. Annals of Nuclear Energy 94, pages 16-21.
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Jaafar EL Bakkali, Tarek EL Bardouni, Seyedmostafa Safavi, Hamid Boukhal, Mohamed Kaddour, Khalid Benaalilou & Essaid Chham. (2016) ERSN-OpenMC, a Java-based GUI for OpenMC Monte Carlo code. Journal of Radiation Research and Applied Sciences 9:3, pages 234-241.
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Yishu Qiu, Xiaotong Shang, Xiao Tang, Jingang Liang & Kan Wang. (2016) Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC code. Annals of Nuclear Energy 87, pages 228-241.
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A. Ivanov, V. Sanchez, R. Stieglitz & K. Ivanov. (2015) Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback. Annals of Nuclear Energy 84, pages 204-219.
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Hyung Jin Shim, Ho Jin Park, Soonwoo Kwon, Geon Ho Seo & Chang Hyo Kim. (2015) McCARD for neutronics design and analysis of research reactor cores. Annals of Nuclear Energy 82, pages 48-53.
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B. Cochet, A. Jinaphanh, L. Heulers & O. Jacquet. (2015) Capabilities overview of the MORET 5 Monte Carlo code. Annals of Nuclear Energy 82, pages 74-84.
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Min Jae Lee, Han Gyu Joo, Deokjung Lee & Kord Smith. (2014) Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation. Annals of Nuclear Energy 65, pages 101-113.
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B. Cochet, A. Jinaphanh, L. Heulers & O. Jacquet. (2014) Capabilities overview of the MORET 5 Monte Carlo code. Capabilities overview of the MORET 5 Monte Carlo code.
Hyung Jin Shim, Ho Jin Park, Soonwoo Kwon, Geon Ho Seo & Chang Hyo Kim. (2014) McCARD for Neutronics Design and Analysis of Research Reactor Cores. McCARD for Neutronics Design and Analysis of Research Reactor Cores.
Ding She, Jingang Liang & Kan Wang. (2013) Undersampling diagnostics by fission matrix in Monte Carlo criticality calculations. Annals of Nuclear Energy 62, pages 321-325.
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Yoshinori MIYOSHI. (2007) Challenge to “the k−effective of the World” Problem ; Enhancement of Nuclear Criticality Safety through Improving the Fission Source Convergence in Monte Carlo Method「世界の実効増倍率」問題への挑戦. Journal of the Atomic Energy Society of Japan 49:10, pages 698-701.
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