OPTIMISATION OF CRITICALITY AND BURNUP CALCULATIONS IN MONK®

Andrew Cox; Albrecht Kyrieleis; Sam Powell-Gill; Simon Richards; Francesco Tantillo

doi:10.1051/epjconf/202124704003

All issues

Volume 247 (2021)

EPJ Web Conf., 247 (2021) 04003

References

Open Access

Issue		EPJ Web Conf. Volume 247, 2021 PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future


Article Number		04003
Number of page(s)		8
Section		Monte Carlo Transport
DOI		https://doi.org/10.1051/epjconf/202124704003
Published online		22 February 2021

MONK - A Monte Carlo Program for Nuclear Criticality Safety and Reactor Physics Analyses, User Guide for Version 10B, (2017). [Google Scholar]
J. Leppanen, “Two Practical Methods for Unionized Energy Grid Construction in Continuous Energy Monte Carlo Neutron Transport Calculation,” Annals of Nuclear Energy, 36, pp. 878–885 (2009). [Google Scholar]
“ANSWERS Software Service, Wood,” http://www.answerssoftwareservice.com (2019). [Google Scholar]
S.D. Richards et al., “MONK and MCBEND: Current status and recent developments,” Annals of Nuclear Energy, 82, pp. 63–73 (2015) [Google Scholar]
“ANSWERS Software Service, Wood,” Variance Reduction - MCBEND11 User Guide, pp. 35–48.,” AMEC, Dorchester (2013). [Google Scholar]
E.E. Lewis and W.F. Miller, Jr., Computational Methods of Neutron Transport, pp. 47–55, American Nuclear Society, Inc., Illinois, U.S.A (1993) [Google Scholar]
M. Nakagawa and T.Mori, “Whole Core Calculations of Power Reactors by Use of Monte Carlo Method,” Journal of Nuclear Science and Technology, 30, pp. 692–701 (1993) [Google Scholar]
C. Dean, R. Perry, R. Neal, A. Kyrieleis, “Validation of Run-Time Doppler Broadening in MONK with JEFF3.1,” Journal of the Korean Physical Society, 59, pp. 1162–1165 (2011). [Google Scholar]

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[1] MONK - A Monte Carlo Program for Nuclear Criticality Safety and Reactor Physics Analyses, User Guide for Version 10B, (2017). [Google Scholar]

[2] J. Leppanen, “Two Practical Methods for Unionized Energy Grid Construction in Continuous Energy Monte Carlo Neutron Transport Calculation,” Annals of Nuclear Energy, 36, pp. 878–885 (2009). [Google Scholar]

[3] “ANSWERS Software Service, Wood,” http://www.answerssoftwareservice.com (2019). [Google Scholar]

[4] S.D. Richards et al., “MONK and MCBEND: Current status and recent developments,” Annals of Nuclear Energy, 82, pp. 63–73 (2015) [Google Scholar]

[5] “ANSWERS Software Service, Wood,” Variance Reduction - MCBEND11 User Guide, pp. 35–48.,” AMEC, Dorchester (2013). [Google Scholar]

[6] E.E. Lewis and W.F. Miller, Jr., Computational Methods of Neutron Transport, pp. 47–55, American Nuclear Society, Inc., Illinois, U.S.A (1993) [Google Scholar]

[7] M. Nakagawa and T.Mori, “Whole Core Calculations of Power Reactors by Use of Monte Carlo Method,” Journal of Nuclear Science and Technology, 30, pp. 692–701 (1993) [Google Scholar]

[8] C. Dean, R. Perry, R. Neal, A. Kyrieleis, “Validation of Run-Time Doppler Broadening in MONK with JEFF3.1,” Journal of the Korean Physical Society, 59, pp. 1162–1165 (2011). [Google Scholar]