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Select papers from the M&C 2023 special issue

Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations

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Received 15 Dec 2023, Accepted 13 Mar 2024, Published online: 08 May 2024

References

  • G. R. KEEPIN, Physics of Nuclear Kinetics, Addison-Wesley (1965).
  • J. J. DUDERSTADT and L. J. HAMILTON, Nuclear Reactor Analysis, Wiley (1976).
  • D. L. HETRICK, Dynamics of Nuclear Reactor, American Nuclear Society (1993).
  • ENDF-6 Formats Manual, M. HERMAN and A. TRKOV, Eds., BNL-90365-2009, Brookhaven National Laboratory (2009).
  • F. JATUFF et al., “Measurement and Interpretation of Delayed Photoneutron Effects in Multizone Criticals with Partial D2O Moderation,” Ann. Nucl. Energy, 30, 17, 1731 (2003); https://doi.org/10.1016/S0306-4549(03)00136-1.
  • A. HAINOUN and I. KHAMIS, “Determination of Neutron Generation Time in Miniature Neutron Source Reactor by Measurement of Neutronics Transfer Function,” Nucl. Eng. Des., 195, 3, 299 (2000); https://doi.org/10.1016/S0029-5493(99)00160-0.
  • A. A. NAHLA, “Generalization of the Analytical Exponential Model to Solve the Point Kinetics Equations of Be- and D2O-Moderated Reactors,” Nucl. Eng. Des., 238, 10, 2648 (2008); https://doi.org/10.1016/j.nucengdes.2008.04.002.
  • R. J. TUTTLE, “Delayed-Neutron Data for Reactor-Physics Analysis,” Nucl. Sci. Eng., 56, 1, 37 (1975); https://doi.org/10.13182/NSE75-A26620.
  • Y. NAUCHI and T. KAMEYAMA, “Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method,” J. Nucl. Sci. Technol., 47, 11, 977 (2010); https://doi.org/10.1080/18811248.2010.9711662.
  • B. C. KIEDROWSKI, F. B. BROWN, and P. P. H. WILSON, “Adjoint-Weighted Tallies for k-Eigenvalue Calculations with Continuous-Energy Monte Carlo,” Nucl. Sci. Eng., 168, 3, 226 (2011); https://doi.org/10.13182/NSE10-22.
  • S. H. CHOI and H. J. SHIM, “Memory-Efficient Calculations of Adjoint-Weighted Tallies by the Monte Carlo Wielandt Method,” Ann. Nucl. Energy, 96, 287 (2016); https://doi.org/10.1016/j.anucene.2016.06.011.
  • H. J. SHIM et al., “Estimation of Kinetics Parameters by Monte Carlo Fixed-Source Calculations for Point Kinetic Analysis of Accelerator-Driven System,” J. Nucl. Sci. Technol., 57, 2, 177 (2020); https://doi.org/10.1080/00223131.2019.1699188.
  • H. HURWITZ, “Physical Interpretation of the Adjoint Flux: Iterated Fission Probability,” Naval Reactor Physics Handbook, Vol. I, pp. 864–869, A. RADKOWSKY, Ed., U.S. Atomic Energy Commission (1964).
  • J. LIEBEROTH, “A Monte Carlo Technique to Solve the Static Eigenvalue Problem of the Boltzmann Transport Equation,” Nukleonik, 11, 213 (1968).
  • H. J. SHIM and C. H. KIM, “Adjoint Sensitivity and Uncertainty Analyses in Monte Carlo Forward Calculations,” J. Nucl. Sci. Technol., 48, 12, 1453 (2011); https://doi.org/10.1080/18811248.2011.9711838.
  • H. J. SHIM et al., “McCARD: Monte Carlo Code for Advanced Reactor Design and Analysis,” Nucl. Eng. Technol., 44, 2, 161 (2012); https://doi.org/10.5516/NET.01.2012.503.
  • M. PEŠIĆ, “RB Reactor: Lattices of 80%-Enriched Uranium Elements in Heavy Water,” NEA/NSC/DOC(95), 3, (2000).
  • N. SHAUKAT, M. RYU, and H. J. SHIM, “Dynamic Monte Carlo Transient Analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD Benchmark,” Nucl. Eng. Technol., 49, 5, 920 (2017); https://doi.org/10.1016/j.net.2017.04.008.
  • S. H. JANG and H. J. SHIM, “Advances for the Time-Dependent Monte Carlo Neutron Transport Analysis in McCARD,” Nucl. Eng. Technol., 55, 7, 2712 (2023); https://doi.org/10.1016/j.net.2023.04.007.
  • I. LUX and L. KOBLINGER, Monte Carlo Particle Transport Methods: Neutron and Photon Calculations, CRC Press (2018).
  • G. I. BELL and S. GLASSTONE, Nuclear Reactor Theory, U.S. Atomic Energy Commission (1970).
  • Z. AKCASU, G. S. LELLOUCHE, and L. M. SHOTKIN, Mathematical Methods in Nuclear Reactor Dynamics, Academic Press (1971).
  • K. O. OTT and R. J. NEUHOLD, Introductory Nuclear Reactor Dynamics, American Nuclear Society (1985).
  • SCALE Code System, V.6.2.4., W. A. WIESELQUIST, R. A. LEFEBVRE, and M. A. JESSEE Eds., pp. 5–118, ORNL/TM-2005/39, Oak Ridge National Laboratory (2020).
  • International Handbook of Evaluated Criticality Safety Benchmark Experiments,” NEA/NSC/DOC(95), 3 (2021).

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