104
Views
0
CrossRef citations to date
0
Altmetric
Research Article

Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique

ORCID Icon &
Pages 1607-1619 | Received 27 Jun 2023, Accepted 27 Sep 2023, Published online: 15 Nov 2023

References

  • X. SHEN et al., “Reactivity Insertion Transient Analysis for KUR Low-Enriched Uranium Silicide Fuel Core,” Ann. Nucl. Energy, 62, 195 (2013); https://doi.org/10.1016/j.anucene.2013.06.014.
  • A. ZOIA et al., “Monte Carlo Method for Reactor Period Calculations,” Ann. Nucl. Energy, 75, 627 (2015); http://dx.doi.org/10.1016/j.anucene.2014.09.014.
  • H. A. KIA et al., “Implementation and Comparison of Different Prompt and Delayed α-Static Approaches,” Prog. Nucl. Energy, 114, 210 (2019); http://dx.doi.org/10.1016/j.pnucene.2019.03.013.
  • Y. NAUCHI, “Attempt of Estimate Reactor Period by Natural Mode Eigenvalue Calculation,” Proc. SNA + MC 2013 Conf., Paris, France, October 27–31, 2013.
  • Y. NAUCHI, A. JINAPHANH, and A. ZOIA, “Comparing the Time-Eigenvalues of the Natural Mode Equation by Weight Balancing and α-k Methods,” Ann. Nucl. Energy, 162, 108486 (2021); http://dx.doi.org/10.1016/j.anucene.2021.108486.
  • C. JOSEY and F. B. BROWN, “Stabilizing the k-Alpha Iteration Algorithm in Very Subcritical Regimes,” Proc. Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2019), p. 948, Portland, Oregon, August 25–29, 2019 (2019).
  • B. R. BETZLER et al., “Calculating Infinite-Medium-Eigenvalue Spectra with Monte Carlo Using a Transition Rate Matrix Method,” Nucl. Eng. Des., 295, 639 (2015); http://dx.doi.org/10.1016/j.nucengdes.2015.07.052.
  • B. R. BETZLER et al., “Calculating Alpha Eigenvalues and Eigenfunctions with a Markov Transition Rate Matrix Monte Carlo Method,” Nucl. Sci. Eng., 192, 115 (2018); http://dx.doi.org/10.1080/00295639.2018.1497397.
  • V. VITALI et al., “Spectral Analysis by Direct and Adjoint Monte Carlo Methods,” Ann. Nucl. Energy, 137, 107033 (2020); http://dx.doi.org/10.1016/j.anucene.2019.107033.
  • I. VARIANSYAH, B. R. BETZLER, and W. R. MARTIN, “Multigroup Constant Calculation with Static α-Eigenvalue Monte Carlo for Time-Dependent Neutron Transport Simulations,” Nucl. Sci. Eng., 194, 1025 (2020); http://dx.doi.org/10.1080/00295639.2020.1743578.
  • S. CARNEY et al., “Theory and Application of the Fission Matrix Method for Continuous-Energy Monte Carlo,” Ann. Nucl. Energy, 73, 423 (2014); http://dx.doi.org/10.1016/j.anucene.2014.07.020.
  • T. YAMAMOTO and Y. MIYOSHI, “An Algorithm of α- and γ-Mode Eigenvalue Calculations by Monte Carlo Method,” Proc. 7th Int. Conf. Nuclear Criticality Safety. (ICNC’03), Japan Atomic Energy Research Institute JAERI-Conf 2003–019 (2003).
  • T. YAMAMOTO, “Higher Order α Mode Eigenvalue Calculation by Monte Carlo Power Iteration,” Prog. Nucl. Sci. Technol., 2, 826 (2011); http://dx.doi.org/10.15669/pnst.2.826.
  • T. YAMAMOTO, “Monte Carlo Algorithm for Buckling Search and Neutron Leakage-Corrected Calculations,” Ann. Nucl. Energy, 47, 14 (2012); http://dx.doi.org/10.1016/j.anucene.2012.04.017.
  • T. UEKI, T. MORI, and M. NAKAGAWA, “Error Estimations and Their Biases in Monte Carlo Eigenvalue Calculations,” Nucl. Sci. Eng., 125, 1 (1997); http://dx.doi.org/10.13182/NSE97-1.
  • T. UEKI, “Intergenerational Correlation in Monte Carlo k-eigenvalue Calculation,” Nucl. Sci. Eng., 141, 101 (2002); http://dx.doi.org/10.13182/NSE141-101.
  • H. J. SHIM and C. H. KIM, “McCARD: Real Variance Estimation Using an Intercycle Fission Source Correlation for Monte Carlo Eigenvalue Calculations,” Nucl. Sci. Eng., 162, 98 (2009); http://dx.doi.org/10.13182/NSE09-2.
  • H. RIEF, “Generalized Monte Carlo Perturbation Algorithms for Correlated Sampling and a Second-Order Taylor Series Approach,” Ann. Nucl. Energy, 9, 455 (1984); http://dx.doi.org/10.1016/0306-4549(84)90064-1.
  • G. W. MCKINNEY and J. L. IVERSON, “Verification of the Monte Carlo Differential Operator Technique for MCNP,” LA-13098, Los Alamos National Laboratory (1996).
  • J. A. FAVORITE, “An Alternative Implementation of the Differential Operator (Taylor Series) Perturbation Methods for Monte Carlo Criticality Problems,” Nucl. Sci. Eng., 142, 327 (2002); http://dx.doi.org/10.13182/NSE02-A2311.
  • Y. NAGAYA and T. MORI, “Impact of Perturbed Fission Source on the Effective Multiplication Factor in Monte Carlo Perturbation Calculations,” J. Nucl. Sci. Technol., 42, 428 (2005); http://dx.doi.org/10.3327/jnst.42.428.
  • K. F. RASKACH, “An Improvement of the Monte Carlo Generalized Differential Operator Method by Taking into Account First- and Second-Order Perturbations of Fission Source,” Nucl. Sci. Eng., 162, 158 (2009); http://dx.doi.org/10.13182/NSE162-158.
  • A. JINAPHANH, N. LECLAIRE, and B. COCHET, “Continuous-Energy Sensitivity Coefficients in the MORET Code,” Nucl. Sci. Eng., 184, 53 (2016); http://dx.doi.org/10.13182/NSE16-2.
  • T. YAMAMOTO and H. SAKAMOTO, “Two-Step Monte Carlo Sensitivity Analysis of Alpha- and Gamma-Eigenvalues with the Differential Operator Sampling Method,” Ann. Nucl. Energy, 133, 100 (2019); http://dx.doi.org/10.1016/j.anucene.2019.05.013.
  • Y. NAGAYA and T. MORI, “Estimation of Sample Reactivity Worth with Differential Operator Sampling Method,” Prog. Nucl. Sci. Technol., 2, 842 (2011); http://dx.doi.org/10.15669/pnst.2.842.
  • B. C. KIEDROWSKI, “Review of Early 21st-Century Monte Carlo Perturbation and Sensitivity Techniques for k-Eigenvalue Radiation Transport Calculations,” Nucl. Sci. Eng., 185, 426 (2017); http://dx.doi.org/10.1080/00295639.2017.1283153.
  • T. YAMAMOTO and H. SAKAMOTO, “A Monte Carlo Technique for Sensitivity Analysis of Alpha-Eigenvalue with the Differential Operator Sampling Method,” Ann. Nucl. Energy, 127, 178 (2019); http://dx.doi.org/10.1016/j.anucene.2018.12.012.
  • T. YAMAMOTO and H. SAKAMOTO, “Monte Carlo Sensitivity Analysis Method for the Effective Delayed Neutron Fraction with the Differential Operator Sampling Method,” Ann. Nucl. Energy, 140, 107108 (2019); http://dx.doi.org/10.1016/j.anucene.2019.107108.
  • K. OKUMURA et al., “SRAC2006: A Comprehensive Neutronics Calculation Code System,” JAEA-Data/Code 2007–004, Japan Atomic Energy Research Institute (2007).
  • K. SHIBATA et al., “JENDL-4.0: A New Library for Nuclear Science and Engineering,” J. Nucl. Sci. Technol., 48, 1 (2011); http://dx.doi.org/10.1080/18811248.2011.9711675.
  • R. E. ALCOUFFE et al., “DANTSYS: A Diffusion Accelerated Neutral Particle Transport Code System,” LA-12969-M, Los Alamos National Laboratory (1995).
  • Y. NAGAYA, K. OKUMURA, and T. MORI, “Recent Developments of JAEA’s Monte Carlo Code MVP for Reactor Physics Applications,” Ann. Nucl. Energy, 82, 85 (2015); http://dx.doi.org/10.1016/j.anucene.2014.09.037.

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.