Nuclear Engineering and Technology

  • 제52권4호
  • /
  • Pages.661-673
  • /
  • 2020
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Simulations of BEAVRS benchmark cycle 2 depletion with MCS/CTF coupling system

  • Yu, Jiankai (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Hyunsuk (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Kim, Hanjoo (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Zhang, Peng (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology) ;
  • Lee, Deokjung (Department of Nuclear Engineering, Ulsan National Institute of Science and Technology)
  • 투고 : 2019.02.05
  • 심사 : 2019.09.17
  • 발행 : 2020.04.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

The quarter-core simulation of BEAVRS Cycle 2 depletion benchmark has been conducted using the MCS/CTF coupling system. MCS/CTF is a cycle-wise Picard iteration based inner-coupling code system, which couples sub-channel T/H (thermal/hydraulic) code CTF as a T/H solver in Monte Carlo neutron transport code MCS. This coupling code system has been previously applied in the BEAVRS benchmark Cycle 1 full-core simulation. The Cycle 2 depletion has been performed with T/H feedback based on the spent fuel materials composition pre-generated by the Cycle 1 depletion simulation using refueling capability of MCS code. Meanwhile, the MCS internal one-dimension T/H solver (MCS/TH1D) has been also applied in the simulation as the reference. In this paper, an analysis of the detailed criticality boron concentration and the axially integrated assembly-wise detector signals will be presented and compared with measured data based on the real operating physical conditions. Moreover, the MCS/CTF simulated results for neutronics and T/H parameters will be also compared to MCS/TH1D to figure out their difference, which proves the practical application of MCS into the BEAVRS benchmark two-cycle depletion simulations.

키워드

참고문헌

  1. H.S. Lee, W.Y. Kim, P. Zhang, et al., Development Status of Monte Carlo Code at UNIST, KNS 2016 Spring Meeting, Jeju, Korea, 2016. May 12-13.
  2. R.K. Salko, CTF Theory Manual, Reactor Dynamics and Fuel Management Group, Pennsylvania State University, 2014.
  3. K.J. Geelhood, W.G. Luscher, FRAPCON-4.0: Integral Assessment, Pacific Northwest National Laboratory, 2015. PNNL-19418.
  4. J. Yu, H. Lee, H. Kim, et al., Preliminary validation of MCS multi-physics coupling capability with CTF, in: Proceedings of the Reactor Physics Asia 2017 (RPHA17) Conference, Chengdu, China, 2017. August. 24-25.
  5. J. Yu, S. Lee, D. Lee, Fuel Performance Coupling of FRAPCON within MCS, Transactions of 2017 ANS Winter Meeting, Washington, D.C., 2017. Oct. 29-Nov. 2.
  6. J. Yu, H. Lee, M. Lemaire, et al., MCS based neutronics/thermal-hydraulics/fuelperformance coupling with CTF and FRAPCON, Comput. Phys. Commun. 238 (2019) 1-18. https://doi.org/10.1016/j.cpc.2019.01.001
  7. CASL, Consortium for advanced simulation of light water reactors (CASL). http://www.casl.gov/, 2015.
  8. S.C. Benjamin, G. Andrew, S. Shane, et al., Simulation of the BEAVRS Benchmark Using VERA, M&C 2017 e International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, 2017. Jeju, Korea, April 16-20.
  9. B. Kochunas, D. Jabaay, T. Downar, et al., Validation and Application of the 3D Neutron Transport MPACT within CASL VERA-CS, Oak Ridge National Laboratory, 2015.
  10. B. Kochunas, B. Collins, S. Stimpson, et al., VERA core simulatormethodology for pressurizedwater reactor cycle depletion, Nucl. Sci. Eng. 185 (1) (2017) 217-231. https://doi.org/10.13182/NSE16-39
  11. J.A. Turner, K. Clarno, M. Sieger, et al., The virtual environment for reactor applications (VERA): design and architecture, J. Comput. Phys. 326 (2016) 544-568, 2016. https://doi.org/10.1016/j.jcp.2016.09.003
  12. B. Kochunas, B. Collins, D. Jabaay, et al., Overview of development and design of MPACT: Michigan parallel characteristics transport code, Proc. M C 2013 (May 5-9, 2013). Sun Valley, ID, USA.
  13. J.D. Hales, S.R. Novascone, B.W. Spencer, et al., Verification of the BISON fuel performance code, Ann. Nucl. Energy 71 (2014) 81-90. https://doi.org/10.1016/j.anucene.2014.03.027
  14. S. Liu, J. Liang, Q. Wu, et al., BEAVRS full core burnup calculation in hot full power condition by RMC code, Ann. Nucl. Energy 101 (2017) 434-446. https://doi.org/10.1016/j.anucene.2016.11.033
  15. S. Liu, J. Yu, J. Liang, et al., Study of neutronics and thermal-hydraulics coupling with RMC COBRA-EN system, in: 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), Ottawa, Ontario, Canada, 2015. October 18-21.
  16. J. Guo, S. Liu, X. Shang, et al., Coupled neutronics/thermal-hydraulics analysis of a full PWR core using RMC and CTF, Ann. Nucl. Energy 109 (2017) 327-336. https://doi.org/10.1016/j.anucene.2017.05.041
  17. K. Wang, S. Liu, Z. Li, et al., Analysis of BEAVRS two-cycle benchmark using RMC based on full core detailed model, Prog. Nucl. Energy 98 (2017) 301-312. https://doi.org/10.1016/j.pnucene.2017.04.009
  18. K. Li, S. Liu, J. Guo, et al., Up-to-Date Results of BEAVRS Two-Cycle Benchmark with Internal Coupling between RMC and CTF, Transactions of 2018 ANS Winter Meeting, Nov.11-15, 2018. Orlando, FL.
  19. H.S. Lee, W.K. Kim, P. Zhang, et al., Preliminary Simulation Results of BEAVRS Three-Dimensional Cycle 1 Wholecore Depletion by UNIST Monte Carlo Code MCS, M&C 2017 - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, 2017. Jeju, Korea, April 16-20, 2017.
  20. N. Horelik, B. Herman, B. Forget, et al., Benchmark for evaluation and validation of reactor simulations (BEAVRS), v1. 0.1, in: Proc. Int. Conf. Mathematics and Computational Methods Applied to Nuc. Sci. & Eng., 2013.
  21. N. Horelik, MIT Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS), Version 2.0, MIT Computational Reactor Physics Group, Massachusetts Institute of Technology, 2016.
  22. N. Horelik, MIT Benchmark for Evaluation and Validation of Reactor Simulations (BEAVRS), Rev. 2.0.2, MIT Computational Reactor Physics Group, Massachusetts Institute of Technology, 2018.
  23. D.J. Kelly, T.M. Sutton, S.C. Wilson, MC21 analysis of the nuclear energy agency Monte Carlo performance benchmark problem, Proc. PHYSOR Adv React. Phys. Link. Res., Ind. Educ. (2012) 15-20.
  24. K. Smith, B. Forget, Challenges in the development of high-fidelity LWR core neutronics tools, in: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2013), Sun Valley, Idaho, USA, 2013. May 5-9.
  25. A. Yamamoto, I. Tsutomu, Impact of pin-by-pin thermal-hydraulic feedback modeling on steady-state core characteristics, Nucl. Technol. 149 (2) (2005) 175-188. https://doi.org/10.13182/NT05-A3588

피인용 문헌

  1. A Robust, Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k-Eigenvalue Calculations-II: Numerical Results vol.195, pp.11, 2020, https://doi.org/10.1080/00295639.2021.1906586