Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

  • Guo, Hui (School of Nuclear Science and Engineering, Shanghai Jiao Tong University) ;
  • Huo, Xingkai (China Institute of Atomic Energy (CIAE)) ;
  • Feng, Kuaiyuan (School of Nuclear Science and Engineering, Shanghai Jiao Tong University) ;
  • Gu, Hanyang (School of Nuclear Science and Engineering, Shanghai Jiao Tong University)
  • Received : 2021.11.09
  • Accepted : 2022.05.20
  • Published : 2022.10.25
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Abstract

High-fidelity nuclear data libraries and neutronics simulation tools are essential for the development of fast reactors. The IAEA coordinated research project on "Neutronics Benchmark of CEFR Start-Up Tests" offers valuable data for the qualification of nuclear data libraries and neutronics codes. This paper focuses on the verification and validation of the CEFR start-up modelling using OpenMC Monte-Carlo code against the experimental measurements. The OpenMC simulation results agree well with the measurements in criticality, control rod worth, sodium void reactivity, temperature reactivity, subassembly swap reactivity, and reaction distribution. In feedback coefficient evaluations, an additional state method shows high consistency with lower uncertainty. Among 122 relative errors in the benchmark of the distribution of nuclear reaction, 104 errors are less than 10% and 84 errors are less than 5%. The results demonstrate the high reliability of OpenMC for its application in fast reactor simulations. In the companion paper, the influence of cross-section libraries is investigated using neutronics modelling in this paper.

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Acknowledgement

This study is sponsored by National Natural Science Foundation of China (No. 12105170) and Shanghai Sailing Program (No. 20YF1420700). The computations in this paper were run on the π 2.0 cluster supported by the Center for High-Performance Computing at Shanghai Jiao Tong University. The data and information presented in the paper are part of the IAEA coordinated research project on ''Neutronics Benchmark of CEFR Start-Up Tests (IAEA CRP-I31032)".

References

  1. IAEA, Fast Reactor Database 2006 Update (No. IAEA-TECDOC-1531), IAEA, Vienna, Austria, 2006.
  2. P. Tsvetkov, 4 - gas-cooled fast reactors, in: I.L. Pioro (Ed.), Handbook of Generation IV Nuclear Reactors, Woodhead Publishing Series in Energy, Woodhead Publishing, 2016, pp. 91-96, https://doi.org/10.1016/B978-0-08-100149-3.00004-5.
  3. C.F. Smith, L. Cinotti, 6 - lead-cooled fast reactor, in: I.L. Pioro (Ed.), Handbook of Generation IV Nuclear Reactors, Woodhead Publishing Series in Energy, Woodhead Publishing, 2016, pp. 119-155, https://doi.org/10.1016/B978-0-08-100149-3.00006-9.
  4. J.L. Kloosterman, Safety assessment of the molten salt fast reactor (SAMOFAR), in: Molten Salt Reactors and Thorium Energy, Elsevier, 2017, pp. 565-570, https://doi.org/10.1016/B978-0-08-101126-3.00020-8.
  5. X. Huo, Technical Specifications for Neutronics Benchmark of CEFR Start-Up Tests (No. IAEA CRP-I31032), CIAE, Beijing, 2019.
  6. P.K. Romano, N.E. Horelik, B.R. Herman, A.G. Nelson, B. Forget, K. Smith, OpenMC: a state-of-the-art Monte Carlo code for research and development, Ann. Nucl. Energy 82 (2015) 90-97, https://doi.org/10.1016/j.anucene.2014.07.048.
  7. T. Quoc Tran, J. Choe, X. Du, H. Lee, D. Lee, Neutronic simulation of China experimental fast reactor start-up tests- part II: MCS code Monte Carlo calculation, Ann. Nucl. Energy 148 (2020), 107710, https://doi.org/10.1016/j.anucene.2020.107710.
  8. X. Du, J. Choe, T.Q. Tran, D. Lee, Neutronic simulation of China Experimental Fast Reactor start-up tests. Part I: SARAX code deterministic calculation, Ann. Nucl. Energy 136 (2020), 107046, https://doi.org/10.1016/j.anucene.2019.107046.
  9. E. Fridman, X. Huo, Dynamic simulation of the CEFR control rod drop experiments with the Monte Carlo code Serpent, Ann. Nucl. Energy 148 (2020), 107707, https://doi.org/10.1016/j.anucene.2020.107707.
  10. H. Guo, X. Jin, X. Huo, H. Gu, H. Wu, Influence of Nuclear Data Library on Neutronics Benchmark of China Experimental Fast Reactor Start-Up Tests, Nucl. Energy Technol (2022) submitted for publication.
  11. A.R. Siegel, K. Smith, P.K. Romano, B. Forget, K.G. Felker, Multi-core performance studies of a Monte Carlo neutron transport code, Int. J. High Perform. Comput. Appl. 28 (2014) 87-96, https://doi.org/10.1177/1094342013492179.
  12. M. Ellis, D. Gaston, B. Forget, K. Smith, Preliminary coupling of the Monte Carlo code OpenMC and the multiphysics object-oriented simulation environment for analyzing Doppler feedback in Monte Carlo simulations, Nucl. Sci. Eng. 185 (2017) 184-193, https://doi.org/10.13182/NSE16-26.
  13. K.S. Chaudri, S.M. Mirza, Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark, Prog. Nucl. Energy 81 (2015) 43-52, https://doi.org/10.1016/j.pnucene.2014.12.018.
  14. T.J. Labossiere-Hickman, B. Forget, Selected VERA Core Physics Benchmarks in OpenMC, Transactions of the American Nuclear Society, 2017.
  15. P. Romano, S. Harper, Nuclear data processing capabilities in OpenMC, EPJ Web Conf. 146 (2017), 06011, https://doi.org/10.1051/epjconf/201714606011.