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Article

Exact Monte Carlo calculation method for K-eigenvalue change using perturbation source method

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Pages 886-898 | Received 17 Dec 2020, Accepted 26 Jan 2021, Published online: 14 Mar 2021

References

  • Kiedrowski BC. Review of early 21st-century Monte Carlo perturbation and sensitivity techniques for k-eigenvalue radiation transport calculations. Nucl Sci Eng. 2017;185(3):426–444.
  • Takahashi H. Monte Carlo method for geometrical perturbation and its application to the pulsed fast reactor. Nucl Sci Eng. 1970;41(2):259–279.
  • Matthes W. Calculation of reactivity perturbations with the Monte Carlo method. Nucl Sci Eng. 1972;47:234–237.
  • Hoffman TJ, Petrie LM, Landers NF, et al. Carlo perturbation source method for reactivity calculations. Nucl Sci Eng. 1978;66:60–66.
  • Nakagawa M, Asaoka T. Improvement of correlated sampling Monte Carlo methods for reactivity calculations. J Nucl Sci Technol. 1978;15;400−410.
  • Preeg WE, Tsang JSK. Comparison of correlated Monte Carlo techniques. Trans Am Nucl Soc. 1982;43:628–629.
  • Rief H. Generalized Monte Carlo perturbation algorithms for correlated sampling and a second-order taylor series approach. Ann Nucl Energy. 1984;9:455–476.
  • Lux I, Koblinger L. Monte Carlo particle transport methods: neutron and photon calculations. Boca Raton, Florida: CRC Press; 1991.
  • McKinney GW, Iverson JL Verification of the Monte Carlo differential operator technique for MCNP, Los Alamos National Laboratory, LA-13098, 1996.
  • Kitada T, Yamane A, Takeda T Improvements of correlated sampling method in Monte Carlo perturbation theory, Proc Int Conf on the Physics of Reactors PHYSOR96, Mito, Ibaraki, Japan, Sep. 16-20, 1996, A-212–A-219, 1996.
  • Favorite JA. An alternative implementation of the differential operator (Taylor series) perturbation method for Monte Carlo criticality problems. Nucl Sci Eng. 2002;142:327–341.
  • Nagaya Y, Mori T. Impact of perturbed fission source on the effective multiplication factor in Monte Carlo perturbation calculations. J Nucl Sci Technol. 2005;42:428–441.
  • Kiedrowski BC, Brown FB, Wilson PPH. Adjoint-weighted tallies for k-eigenvalue calculations with continuous-energy Monte Carlo. Nucl Sci Eng. 2011;168:226–241.
  • Terranova N, Mancusi D, Zoia A. New perturbation and sensitivity capabilities in TRIPOLI-4®. Ann Nucl Energy. 2018;121:335–349.
  • Kim SH, Yamanaka M, Pyeon CH. Improvement of fission source distribution by correlated sampling method in Monte Carlo perturbation calculations. J Nucl Sci Technol. 2018;55:945–954.
  • Nauchi Y, Kameyama T. Development of calculation technique for iterated fission probability and reactor kinetic parameters using continuous-energy Monte Carlo method. J Nucl Sci Technol. 2010;47:977–990.
  • Shim HJ, Kim CH. Adjoint sensitivity and uncertainty analyses in Monte Carlo forward calculations. J Nucl Sci Technol. 2011;48:1453–1461.
  • Choi SH, Shim HJ. Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method. Ann Nucl Energy. 2016;96:287–294.
  • Qiu Y, Shang X, Tang X, et al. Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC code. Ann Nucl Energy. 2016;87:228–241.
  • Sakamoto H, Yamamoto T. Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems. J Compt Phys. 2017;345:245–259.
  • Yamamoto T, Sakamoto H. Monte Carlo perturbation calculation for geometry change in fixed source problems with the perturbation source method. Prog Nucl Energy. 2021;132:103611.
  • Nagaya Y, Mori T. Estimation of sample reactivity worth with differential operator sampling method. Prog Nucl Sci Technol. 2011;2:842–850.
  • Favorite JA, Parsons DK Second-order cross terms in Monte Carlo differential operator perturbation estimates, Proc M&C 2001, Salt Lake City, Utah, September 2001.
  • Bell GI, Glasstone S. Nuclear reactor theory. New York: Van Norstrand Reinhold; 1970.
  • Truchet G Continuous-energy adjoint flux and perturbation calculation using the iterated fission probability method in Monte Carlo code TRIPOLI-4 and underlying applications. Proc Joint Int Conf on Supercomputing in Nuclear Applications and Monte Carlo 2013 (SNA + MC 2013), Paris, France, October 2013.
  • Truchet G, Leconte P, Palau JM, et al. Sodium void reactivity effect analysis using the newly developed exact perturbation theory in Monte-Carlo code TRIPOLI-4®. Proc PHYSOR 2014 - The Role of Reactor Physics toward a Sustainable Future, Kyoto, Japan, September 2014.
  • Alcouffe RE, Baker RS, Brinkley FW, et al. DANTSYS: a diffusion accelerated neutral particle transport code system. LA-12969-M. 1995.
  • Okumura K, Kugo T, Kaneno K, et al. SRAC2006: a comprehensive neutronics calculation code system. JAEA-Data/Code 2007-004. 2007.

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