Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis
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The critical rod position search has been one of the issues in the Monte Carlo (MC) reactor analysis. This paper proposes a practical and simple approach for the critical rod position search based on the neutron balance equation and the monotonic relation between the control rod absorption rate and the total rod insertion length. The proposed method was implemented in an inline manner within the McCARD, the MC reactor design code, so that the critical rod position is calculated and updated for each fission source iteration. The numerical results in a typical fast reactor problem demonstrate the promising performance of the proposed method in the critical rod position search calculation. Furthermore, the cycle depletion calculation was performed to show the capability of the McCARD to simulate the rodded operation condition. By addressing the critical rod position search problem through the neutron balance approach, the applicability of the MC code in the advanced reactor design will be expanded.
Abstract
The critical rod position search has been one of the issues in the Monte Carlo (MC) reactor analysis. This paper proposes a practical and simple approach for the critical rod position search based on the neutron balance equation and the monotonic relation between the control rod absorption rate and the total rod insertion length. The proposed method was implemented in an inline manner within the McCARD, the MC reactor design code, so that the critical rod position is calculated and updated for each fission source iteration. The numerical results in a typical fast reactor problem demonstrate the promising performance of the proposed method in the critical rod position search calculation. Furthermore, the cycle depletion calculation was performed to show the capability of the McCARD to simulate the rodded operation condition. By addressing the critical rod position search problem through the neutron balance approach, the applicability of the MC code in the advanced reactor design will be expanded.
참고문헌 (22)
- H. O. Kang, "Light water SMR development status in Korea", Nucl. Eng. Des, 419, pp.1~11 (2024)
- "MCNP Code Version 6.3.0, Theory & User Manual", LANL, ~ (2022)
- P. K. Romano, "OpenMC : a state-of-the-art Monte Carlo code for research and development", Ann. Nucl. Energy, 82, pp.90~97 (2015)
- K. Wang, "Rmc – a Monte Carlo code for reactor core analysis", Ann. Nucl. Energy, 82, pp.121~129 (2015)
- Y. Wu, "CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC", Ann. Nucl. Energy, 82, pp.161~168 (2015)
- J. Lepp¨anen, "The Serpent Monte Carlo code: status, development and applications in 2013", Ann. Nucl. Energy, 82, pp.142~150 (2015)
- H. Shim, "McCARD : Monte Carlo code for advanced reactor design and analysis", Nucl. Eng. Technol, 44(2), pp.161~176 (2012)
- H. Lee, "Mcs – a Monte Carlo particle transport code for large-scale power reactor analysis", Ann. Nucl. Energy, 139, pp.107276~ (2020)
- N. Choi, "Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation", Nucl. Eng. Technol, 52, pp.2667~2677 (2020)
- D. F. Gill, "Movable geometry and eigenvalue search capability in the MC21 Monte Carlo Code", Proc. Intl. Conf. On Mathematics and Computational Methods Applied to Nuclear Science and Engineering (2013)
- User Guide to the Advanced Dimensional Depletion for Engineering of Reactors(ADDER)Software, "K. Anderson", Argonne National Laboratory, ~, pp.ANL (2022), RTR[DOI]
- D. Price, "Method for control drum position critical search with Monte Carlo codes", Prog. Nucl. Energy, 162, pp.104731~ (2023)
- R. Li, "A new algorithm of critical control rod position search in MC code", Ann. Nucl. Energy, 204, pp.110572~ (2024)
- A. Dall’Osso, "A neutron balance approach in critical parameter determination", Ann. Nucl. Energy, 33, pp.1686~1694 (2008)
- L. Rui, "Criticality search of soluble boron iteration in MC code JMCT", Energy Proc, 127, pp.329~334 (2017)
- Y. G. Jo, "Inline critical boron concentration search with p-CMFD feedback in whole-core continuous-energy Monte Carlo simulation", Ann. Nucl. Energy, 120, pp.402~409 (2018)
- M. B. Chadwick, "ENDF", B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, 2011, pp.112, 2887~2996
- T. Ueki, "Autocorrelation and dominance ratio in Monte Carlo criticality calculations", Nucl. Sci. Eng, 145, pp.279~290 (2003)
- F. Brown, "K-Effective of the world and other concerns for Monte Carlo eigenvalue calculations", Progress in Nuclear Science and Technology, 2, pp.738~742 (2011)
- M. Pusa, "Higher-order Chebyshev rational approximation method and application to burnup equations", Nucl. Sci. Eng, 182(3), pp.297~318 (2016)
- Preliminary control rod life time considerations for the versatile test reactor, "Z. Zhong", Argonne National Laboratory, ~, pp.ANL-VTR-11 (2018)
- H.J. Shim, "Stochastic error propagation model for Monte Carlo eigenvalue calculations with feedback updates", Transactions of the Korean Nuclear Society Autumn Meeting (2019)