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BEAVRS benchmark analyses by DeCART stand-alone calculations and comparison with DeCART/MATRA multi-physics coupling calculations

  • 투고 : 2019.11.12
  • 심사 : 2020.02.21
  • 발행 : 2020.09.25

초록

The BEAVRS (Benchmark for Evaluation and Validation of Reactor Simulation) benchmark calculations were performed by DeCART stand-alone and DeCART/MATRA multi-physics coupled code system to verify their accuracy. The solutions of DeCART stand-alone calculations for the control rod bank worth, detector signal, isothermal temperature coefficient, and critical boron concentration agreed very well with the measurements. The root-mean-square errors of the boron letdown curves for two-cycles were less than about 20 ppm, while the individual and total control rod bank worth agreed well within 7.3% and 2.4%, respectively. For the BEAVRS benchmark calculations at the beginning of burnup, the difference between DeCART simplified thermal-hydraulic stand-alone and DeCART/MATRA coupled calculations were not significantly large. Therefore, it is concluded that both the DeCART stand-alone code and the DeCART/MATRA multi-physics coupled code system have the capabilities to generate high fidelity transport solutions at core follow calculations.

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참고문헌

  1. S.J. Kim, et al., Preliminary coupling of MATRA code for multi-physics analysis, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 29-30, 2014.
  2. J.Y. Cho, et al., "DeCART v1.2 User's Manual," KAERI/TR-3438/2007, 2007.
  3. H.G. Joo, et al., "Methods and Performance of a Three-Dimensional Whole-Core Transport Code DeCART," PHYSOR 2004 - the Physics of Fuel Cycles and Advanced Nuclear System, Global Developments, Chicago, Illinois, 2004. April 25-29.
  4. S.J. Kim, et al., Development and Assessment of Core T/H Code's Real Time Model for SMART Simulator, 2013. KAERI/TR-4904/2013.
  5. D.N. Horelik, et al., Benchmark for evaluation and validation of reactor simulations, MIT Computational Reactor Physics Group, rev03 29 (August) (2018).
  6. B.S. Collins, et al., Simulation of the BEAVRS benchmark using VERA, in: International Conference on Mathematics & Computational Method Applied to Nuclear Science and Engineering (M&C 2017), Jeju, Korea, April 16-20, 2017.
  7. M. Ryu, et al., Solutions of the BEAVRS benchmark using the nTRACER direct whole core calculation code, J. Nucl. Sci. Technol. 52 (2015) 961-969. https://doi.org/10.1080/00223131.2015.1038664
  8. P. Darnowski, et al., Analysis of the BEAVR PWR benchmark using SCALE and PARCS, Nukleonika 64 (3) (2019) 87. https://doi.org/10.2478/nuka-2019-0011
  9. S. Kumar, et al., Integral Full Core Multi-Physics PWR Benchmark with Measured Data, 2018. NEUP 14-6741.
  10. J. Leppanen, et al., Validation of the serpent-ARES code sequence using the MIT BEAVRS benchmark e initial core at HZP conditions, Ann. Nucl. Energy 69 (2014) 212-225. https://doi.org/10.1016/j.anucene.2014.02.014
  11. H. Lee, et al., MCS - a Monte Carlo particle transport code for large-scale power reactor analysis, Ann. Nucl. Energy 139 (2020) 107276. https://doi.org/10.1016/j.anucene.2019.107276
  12. S. Choi, et al., Preliminary Results of BEAVRS Whole-Core Multi-Cycle Analysis with Neutron Transport Code System, 2019. M&C2019, Portland, OR, USA, August 25-29.
  13. D.J. Kelly, et al., Analysis of select BEAVRS PWR benchmark cycle 1 results using MC21 and OpenMC, 2014. PHYSOR2014 - the role of reactor physics toward a sustainable future, Kyoto, Japan, September 28 - October 3.
  14. H.J. Park, et al., Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark, Ann. Nucl. Energy 90 (2016) 205-211. https://doi.org/10.1016/j.anucene.2015.12.009
  15. H.J. Park, et al., An improved DeCART library generation procedure with explicit resonance interference using continuous energy Monte Carlo calculation, Ann. Nucl. Energy 105 (2017) 95-105. https://doi.org/10.1016/j.anucene.2017.03.012
  16. S. Choi, et al., Resonance treatment using pin-based pointwise energy slowing-down method, J. Comput. Phys. 330 (2017) 134-155. https://doi.org/10.1016/j.jcp.2016.11.007
  17. K.S. Kim, S.G. Hong, A new procedure to generate resonance integral table with an explicit resonance interference for transport lattice code, Ann. Nucl. Energy 38 (2011) 118-127. https://doi.org/10.1016/j.anucene.2010.08.005
  18. D. Hwang, et al., Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA, vol. 2012, Science and Technology of Nuclear Installation, 2012. Article ID 603752.
  19. H. Finnemann, A. Galati, "NEACRP 3-D LWR Core Transient Benchmark," NEACRP-L-335, 1992. Revision 1.
  20. C.A. Meyer, et al., 1967 ASME Steam Table, American Society of Mechanical Engineers, New York, 1968.
  21. H.J. Shim, et al., McCARD: an Monte Carlo code for advanced reactor design and analysis, Nucl. Eng. Tech. 44 (2) (2012) 161-176. https://doi.org/10.5516/NET.01.2012.503
  22. New York Power, Indian Point 3 Nuclear Power Plant Cycle 11 Physics Test Report, New York Power Authority, 2000.
  23. D.C. Groeneveld, et al., The 1995 look-up table for critical heat flux in tubes, Nucl. Eng. Des. 163 (1996) 1-23. https://doi.org/10.1016/0029-5493(95)01154-4
  24. A. Graham, et al., Assessment of Thermal-Hydraulic Feedback Models, PHYSOR2016, Sun Valley, ID, USA, 2016. May 1-5.

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