DOI QR코드

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Sensitivity study of parameters important to Molten Salt Reactor Safety

  • 투고 : 2022.10.19
  • 심사 : 2023.02.02
  • 발행 : 2023.05.25

초록

This paper presents a molten salt reactor (MSR) design parameter sensitivity study using a nodal dynamic modelling methodology with explicitly modified point kinetics equation and Mann's model for heat transfer. Six parameters that can impact MSR safety are evaluated. A MATLAB-Simulink model inspired by Thorcon's 550MWth MSR is used for parameter evaluations. A safety envelope was formed to encapsulate power, maximum and minimum temperature, and temperature-induced reactivity feedback. The parameters are perturbed by ±30%. The parameters were then ranked by their subsequent impact on the considered safety envelope, which ranks acceptable parameter uncertainty. The model is openly available on GitHub.

키워드

과제정보

This research was supported by the US Department of Energy's Oak Ridge National Laboratory managed by UT-Battelle LLC (contract number 00OR22725). The work was sponsored through a subcontract with the University of Tennessee from the US Department of Energy Office of Nuclear Energy, Advanced Reactor Technologies Molten Salt Reactor Program.

참고문헌

  1. E.S. Bettis, R.W. Schroeder, G.A. Cristy, H.W. Savage, R.G. Affel, L.F. Hemphill, The aircraft reactor experimentddesign and construction, Nuclear Science and Engineering 2 (6) (1957) 804-825. https://doi.org/10.13182/NSE57-A35495
  2. P.N. Haubenreich, J.R. Engel, Experience with the molten-salt reactor experiment, Nuclear Applications and Technology 8 (2) (1970) 118-136. https://doi.org/10.13182/NT8-2-118
  3. Shanghai institute of applied physics, Chinese academy of sciences. http://english.sinap.cas.cn/about_sinap/brief_introduction/. (Accessed 19 December 2022).
  4. TerraPower, Terrapower and southern company to demonstrate the world's first fast-spectrum salt reactor at Idaho national laboratory. https://www.terrapower.com/southern-terrapower-mcre-agreement. (Accessed 19 December 2022).
  5. Next: nuclear energy experimental testing. https://www.acunextlab.org/. (Accessed 19 December 2022).
  6. N. Dunkle, J. Richardson, V. Pathirana, A. Wheeler, O. Chvala, S.E. Skutnik, Nerthus thermal spectrum molten salt reactor neutronics and dynamic model, review in Nuclear Engineering and Design.
  7. M.A. Rose, S.E. Creasman, Report on Data Quality Required for Modeling an Msr," Tech. Rep. ANL/CFCT-22/17, Argonne National Laboratory (ANL), Argonne, IL, USA, July 2022.
  8. Sensitivity Study Repository, 2022. https://github.com/sjj158/2022-SensitivityStudy.
  9. V. Singh, A.M. Wheeler, B.R. Upadhyaya, O. Chvala, M.S. Greenwood, Plantlevel dynamic modeling of a commercial-scale molten salt reactor system, Nuclear Engineering and Design 360 (2020), 110457.
  10. S.J. Ball, Approximate models for distributed-parameter heat-transfer systems, ISA Transactions 3 (1) (1964) 38-47.
  11. J. Macphee, The kinetics of circulating fuel reactors, Nuclear Science and Engineering 4 (4) (1958) 588-597. https://doi.org/10.13182/NSE4-588-597
  12. V. Pathirana, O. Chvala, S. Skutnik, Depletion dependency of molten salt reactor dynamics, Annals of Nuclear Energy 168 (2022), 108852.
  13. V. Pathirana, O. Chvala, A.M. Wheeler, Scalable modular dynamic molten salt reactor system model with decay heat, Annals of Nuclear Energy 154 (2021), 108060.
  14. R.C. Robertson, Msre Design and Operations Report Part I Description of Reactor Design," Tech. Rep. ORNL-TM-728, Oak Ridge National Laboratory (ORNL), Oak Ridge, TN, USA, January, 1965.
  15. Coastal Chemical Co. LLC, HITEC® heat transfer salt. https://coastalchem.com/products/heat-transfer-fluids/hitec-heat-transfer-salt/.
  16. V. Pathirana, C. Fontaine-Holl, O. Chvala, Molten Salt Reactor Kinetics in Zero Power Approximation," 2021 ANS Winter Meeting December 1, 2021, vol. 12, Reactor Physics of Advanced Reactors, 2021.
  17. T.W. Kerlin, S.J. Ball, R.C. Steffy, Theoretical dynamics analysis of the moltensalt reactor experiment, Nuclear Technology 10 (1970) 118-132. https://doi.org/10.13182/NT71-A30920
  18. P. Haubenreich, J. Engel, Safety Calculations for Msre," Tech. Rep. ORNL-TM251, Oak Ridge National Laboratory (ORNL), Oak Ridge, TN, USA, May 1962.
  19. V. Singh, A.M. Wheeler, M.R. Lish, O. Chvala, B.R. Upadhyaya, Nonlinear dy-namic model of molten-salt reactor experimentevalidation and operational analysis, Annals of Nuclear Energy 113 (2018) 177-193. https://doi.org/10.1016/j.anucene.2017.10.047
  20. N.R. Brown, D.J. Diamond, S. Bajorek, R. Denning, Thermal-hydraulic and neutronic phenomena important in modeling and simulation of liquid-fuel molten salt reactors, Nuclear Technology 206 (2) (2020) 322-338. https://doi.org/10.1080/00295450.2019.1590077