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A Method to Estimate the Burnup Using Initial Enrichment, Cooling Time, Total Neutron Source Intensity and Gamma Source Activities in Spent Fuels

  • 투고 : 2022.11.29
  • 심사 : 2023.05.02
  • 발행 : 2023.09.30

초록

Spent fuels (SFs) are stored in a storage pool after discharge from nuclear power plants. They can be transferred to for the further processes such as dry storage sites, processing plants, or disposal sites. One of important measures of SF is the burnup. Since the radioactivity of SF is strongly dependent on its burnup, the burnup of SF should be well estimated for the safe management, storage, and final disposal. Published papers about the methodology for the burnup estimation from the known activities of important radioactive sources are somewhat rare. In this study, we analyzed the dependency of the burnup on the important radiation source activities using ORIGEN-ARP, and suggested simple correlations that relate the burnup and the important source activities directly. A burnup estimation equation is suggested for PWR fuels relating burnup with total neutron source intensity (TNSI), initial enrichment, and cooling time. And three burnup estimation equations for major gamma sources, 137Cs, 134Cs, and 154Eu are also suggested.

키워드

과제정보

This work was partly supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (20222B10100060, Development of On-site Burn-up Detection System for the Spent Fuel).

참고문헌

  1. S.M. Bowman and I.C. Gauld, OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations With SCALE/ORIGEN, Oak Ridge National Laboratory, ORNL/TM-2010/43 (2010).
  2. B.B. Bevard, J.C. Wagner, C.V. Parks, and M. Aissa, Review of Information for Spent Nuclear Fuel Burnup Confirmation, U.S. Nuclear Regulatory Commission, NUREG-CR-6998 (2009).
  3. H. Yun, D.Y. Kim, K. Park, and S.G. Hong, "A Criticality Analysis of the GBC-32 Dry Storage Cask With Han-bit Nuclear Power Plant Unit 3 Fuel Assemblies From the Viewpoint of Burnup Credit", Nucl. Eng. Technol., 48(3), 624-634 (2016). https://doi.org/10.1016/j.net.2016.01.011
  4. International Atomic Energy Agency, "Practices and Developments in Spent Fuel Burnup Credit Applications", Proc. of an Technical Committee Meeting, IAEA-TECDOC-1378, April 22-26, 2002, Madrid.
  5. Y. Nakahara, K. Suyama, and T. Suzaki. Translation of Technical Development on Burn-up Credit for Spent LWR Fuels, Oak Ridge National Laboratory Technical Report, ORNL/TR-2001/01 (2001).
  6. S.K. Smith, A. Nicholson, S. Croft, and G. Nutter. High-resolution Gamma Spectroscopy Measurements of Pressurized Water Reactor Spent Nuclear Fuel Rods, Oak Ridge National Laboratory Report (1996).
  7. T. Makmal, O. Aviv, and E. Gilad, "A Simple Gamma Spectrometry Method for Evaluating the Burnup of MTR-type HEU Fuel Elements", Nucl. Instrum. Methods Phys. Res. A, 834, 175-182 (2016). https://doi.org/10.1016/j.nima.2016.08.023
  8. M. Koleska, L. Viererbl, M. Marek, J. Ernest, M. Sunka, and M. Vins, "Determination of IRT-2M Fuel Burnup by Gamma Spectrometry", Appl. Radiat. Isot., 107, 92-97 (2016). https://doi.org/10.1016/j.apradiso.2015.10.001
  9. W.H. Yan, L.G. Zhang, Z. Zhang, and Z.G. Xiao, "Feasibility Studies on the Burnup Measurement of Fuel Pebbles With HPGe Gamma Spectrometer", Nucl. Instrum. Methods Phys. Res. A, 712, 130-136 (2013). https://doi.org/10.1016/j.nima.2013.02.009
  10. P.H. Liem, S. Amini, A.G. Hutagaol, and T.M. Sembiring, "Nondestructive Burnup Verification by Gammaray Spectroscopy of LEU Silicide Fuel Plates Irradiated in the RSG GAS Multipurpose Reactor", Ann. Nucl. Energy, 56, 57-65 (2013). https://doi.org/10.1016/j.anucene.2013.01.013
  11. A. Favalli, D. Vo, B. Grogan, P. Jansson, H. Liljenfeldt, V. Mozin, P. Schwalbach, A. Sjoland, S.J. Tobin, H. Trellue, and S. Vaccaro, "Determining Initial Enrichment, Burnup, and Cooling Time of Pressurized-Water-Reactor Spent Fuel Assemblies by Analyzing Passive Gamma Spectra Measured at the Clab Interim-fuel Storage Facility in Sweden", Nucl. Instrum. Methods Phys. Res. A, 820, 102-111 (2016). https://doi.org/10.1016/j.nima.2016.02.072
  12. H. Trellue, G. McMath, A. Trahan, A. Favalli, T. Burr, A. Sjoland, and U. Backstrom, "Spent Fuel Nondestructive Assay Integrated Characterization From Active Neutron, Passive Neutron, and Passive Gamma", Nucl. Instrum. Methods Phys. Res. A, 988, 164937 (2021).
  13. C.A. Miller, W.A. Peters, F.Y. Odeh, T.H. Shin, M. Mamtimin, S.D. Clarke, T.L. Grimm, and S.A. Pozzi, "Sub-Critical Assembly Die-Away Analysis With Organic Scintillators", Nucl. Instrum. Methods Phys. Res. A, 959, 163598 (2020).
  14. A. Ohzu, M. Maeda, M. Komeda, Y. Toh, M. Koizumi, and M. Seya, "Development of Differential Die-Away Technique in an Integrated Active Neutron NDA System for Nuclear Non-Proliferation and Nuclear Security", IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 1-4, October 21-28, 2017, Georgia.
  15. J. Hu, R. McElroy Jr., A.D. Nicholson, and S. Croft. Fork Experiments in the Hot Cell Using Spent Fuel Rods for International Nuclear Safeguards, Oak Ridge National Laboratory Technical Report, ORNL/SPR2020/1774 (2021).
  16. S. Vaccaro, I.C. Gauld, J. Hu, P. de Baere, J. Peterson, P. Schwalbach, A. Smejkal, A. Tomanin, A. Sjoland, S. Tobin, and D. Wiarda, "Advancing the Fork Detector for Quantitative Spent Nuclear Fuel Verification", Nucl. Instrum. Methods Phys. Res. A, 888, 202-217 (2018). https://doi.org/10.1016/j.nima.2018.01.066
  17. T.W. Doering and G.A. Cordes, Status of the Multi-Detector Analysis System (MDAS) and the Fork Detector Research Programs, 286-297, IAEA-TECDOC-1241 (2000).
  18. A.G. Croff, M.A. Bjerke, G.W. Morrison, and L.M. Petrie. Revised Uranium-Plutonium Cycle PWR and BWR Models for the ORIGEN Computer Code, Oak Ridge National Laboratory Report, ORNL/TM-6051 (1978).
  19. Korea Hydro and Nuclear Power. Preliminary Evaluation of Spent Fuel and Defective Fuel Dry Storage Containers With High Burn-up, Korea Hydro and Nuclear Power Report (2021).
  20. S.H. Cha and K.H. Park, "An Analysis of Neutron Sources and Gamma-ray in Spent Fuels Uing SCALE-ORIGEN-ARP", J. Surf. Sci. Eng., 56(1), 84-93 (2023).