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On-the-fly energy release per fission model in STREAM with explicit neutron and photon heating

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초록

The on-the-fly energy release per fission (OTFK) model is implemented in STREAM to continuously update the Kappa values during the depletion calculation. The explicit neutron and photon energy distribution, which has not been considered in previous STREAM versions, is incorporated into the existing on-the-fly model. The impacts of the modified OTFK model with explicit neutron and photon heating in STREAM on the power distribution, fuel temperature, and other core parameters during depletion with feedback calculations are studied using several problems from the VERA benchmark suit. Overall, the explicit heating calculation provides a better power map for the feedback calculations particularly when strong gamma emitters are present. Generally, the fuel temperature decreases when neutron and photon heating is employed because fission neutrons and gamma rays are transported away from their points of generation. This energy release model in STREAM indicates that gamma energy accounts for approximately 9.5%e10% of the total energy released, and approximately 2.4%e2.6% of the total energy released will be deposited in the coolant for the VERA 5, NuScale, and Yonggwang Unit 3 2D cores.

Abstract

The on-the-fly energy release per fission (OTFK) model is implemented in STREAM to continuously update the Kappa values during the depletion calculation. The explicit neutron and photon energy distribution, which has not been considered in previous STREAM versions, is incorporated into the existing on-the-fly model. The impacts of the modified OTFK model with explicit neutron and photon heating in STREAM on the power distribution, fuel temperature, and other core parameters during depletion with feedback calculations are studied using several problems from the VERA benchmark suit. Overall, the explicit heating calculation provides a better power map for the feedback calculations particularly when strong gamma emitters are present. Generally, the fuel temperature decreases when neutron and photon heating is employed because fission neutrons and gamma rays are transported away from their points of generation. This energy release model in STREAM indicates that gamma energy accounts for approximately 9.5%e10% of the total energy released, and approximately 2.4%e2.6% of the total energy released will be deposited in the coolant for the VERA 5, NuScale, and Yonggwang Unit 3 2D cores.

참고문헌 (40)

  1. Q-Value (MeV, "fission) Determination for the Advanced Test Reactor", J. Sterbentz, 2013, No. INL[DOI]
  2. D. P. Griesheimer, "Self-consistent energy normalization for quasistatic reactor calculations", Journal of Nuclear Engineering, 2(2), pp.215~224 (2021)
  3. L. Ghasabyan, "Use of SERPENT Monte-Carlo code for development of 3D full-core models of Gen-IV fast spectrum reactors and preparation of safety parameters", cross-section data for transient analysis with FAST code system, 2013, ~
  4. Neutron Capture Energies for Flux Normalization and Approximate Model for Gamma-Smeared Power, "K. S. Kim", Oak Ridge National Lab (ORNL), ~, pp.No. ORNL (2018), SPR-2017[DOI]
  5. J. Rhodes, "CASMO-5 energy release per fission model", Proceedings of PHYSOR2008 (2008)
  6. J. Rhodes, "CASMO-5 development and applications", Proceedings of the PHYSOR-2006 Conference, ANS Topical Meeting on Reactor Physics (2006)
  7. 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(12), 2887~2996
  8. S. Choi, "Three-dimensional method of characteristics", diamonddifference transport analysis method in STREAM for whole-core neutron transport calculation, 2021, pp.260, 107332~
  9. S. Choi, "Development of high-fidelity neutron transport code STREAM", Comput. Phys. Commun, 264, pp.107915~ (2021)
  10. J. Leppanen, "Development of a coupled neutron", photon transport mode in the serpent 2 Monte Carlo code, 2017, ~[DOI]
  11. C. Liegeard, "Impact of photon transport on power distribution", Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2017 (2017)
  12. The ARCADIA® reactor analysis system for PWRs methodology description and benchmarking results, "AREVA NP INC", Areva NP Inc, 10~11 (2010)
  13. Y. Liu, "Improved MPACT energy deposition and explicit heat generation coupling with CTF", Ann. Nucl. Energy, 152, pp.107999~ (2021)
  14. B. A. Lindley, "Current status of the reactor physics code WIMS and recent developments", Ann. Nucl. Energy, 102, pp.148~157 (2017)
  15. S. Jae, "Implementation and verification of explicit treatment of neutron", photon heating in nTRACER, 2020, ~
  16. R. Tuominen, "New energy deposition treatment in the Serpent 2 Monte Carlo transport code", Ann. Nucl. Energy, 129, pp.224~232 (2019)
  17. "OpenMC Theory and Methodology"[URL]
  18. T. Goorley, "Initial MCNP6 release overview", Nucl. Tech, 180(3), pp.298~315 (2012)
  19. D.H. Lee, "McCARD gamma transport analysis for RFNC photon spectrum benchmark", Transactions of the Korean Nuclear Society Autumn Meeting (2018)
  20. 마튜 르메르, "Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF", B-VIII.0 and Monte Carlo code MCS, 2020, pp.52(7), 1355~1366[DOI]
  21. Monte Carlo-Advances and Challenges, "F.B. Brown", Los Alamos National Lab (LANL), ~, pp.LA-UR-08-05891 (2008)
  22. Nhan Nguyen Trong Mai, "Analysis of several VERA benchmark problems with the photon transport capability of STREAM", Nuclear Engineering and Technology, 54(7), pp.2670~2689 (2022), 한국원자력학회[DOI]
  23. VERA Core Physics Benchmark Progression Problem Specifications, "A.T. Godfrey", CASL, ~, pp.CASL-U-2012-0131-004 (2014)
  24. B. Ebiwonjumi, "Validation of lattice physics code STREAM for predicting pressurized water reactor spent nuclear fuel isotopic inventory", Ann. Nucl. Energy, 120, pp.431~449 (2018)
  25. B. Ebiwonjumi, "Verification and validation of radiation source term capabilities in STREAM", Ann. Nucl. Energy, 124, pp.80~87 (2019)
  26. NuScale Plant Design Overview, , U.S. Nuclear Regulatory Commission, ~, pp.NP-ER-0000-1198 (2012)
  27. Nuclear Design Report for Yonggwang Unit 3, Cycle 1, "S. K. Lee", Korea Atomic Energy Research Institute (KAERI), ~ (1995)
  28. Fission-energy Release for 16 Fissioning Nuclides, "R. Sher", Stanford Univ., Dept. of Mechanical Engineering, ~, pp.No. EPRI-NP-1771 (1981)
  29. ENDF-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data Files, "A. Trkov", Brookhaven National Lab.(BNL), ~, pp.No. BNL-203218-2018-INRE (2018)
  30. K. Kim, "Generation of a multigroup gamma production and photon transport library for STREAM", Transactions of the Korean Nuclear Society Virtual Spring Meeting (2020)
  31. NJOY2016, "A. C. Kahler III", Los Alamos National Lab (LANL), ~, pp.No. NJOY, NJOY16; 005075MLTPL00 (2016)
  32. H. Lee, "Mcs-a Monte Carlo particle transport code for large-scale power reactor analysis", Ann. Nucl. Energy, 139, pp.107276~ (2020)
  33. X. Wang, "Energy deposition analysis for VERA progression problems by MCNP", Proceedings of PHYSOR 2018 (2018)
  34. D. A. Brown, "ENDF", B-VIII. 0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, 2018, pp.148, 1~142
  35. S. Choi, "Resonance treatment using pin-based pointwise energy slowing-down method", J. Comput. Phys, 330, pp.134~155 (2017)
  36. S. Kinast, "Energy deposition in coolant of PWR under normal operation and accident conditions", Nucl. Eng. Des, 384, pp.111479~ (2021)
  37. D. Lee, "Quadratic depletion method for gadolinium isotopes in CASMO-5", Nucl. Sci. Eng, 174(1), pp.79~86 (2013)
  38. 장재림, "Validation of spent nuclear fuel decay heat calculation by a two-step method", Nuclear Engineering and Technology, 53(1), pp.44~60 (2021), 한국원자력학회[DOI]
  39. Measurements of Decay Heat in Spent Nuclear Fuel at the Swedish Central Interim Storage Facility, Clab, "Swedish Nuclear Fuel and Waste Management Company", SKB, ~, pp.Rapport R-05-62
  40. Validation of SCALE 5 Decay Heat Predictions for LWR Spent Nuclear Fuel, "I.C. Gauld", Nuclear Regulatory Commission, ~, pp.ORNL, TM-2006[DOI]

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