한국표면공학회지 (Journal of the Korean institute of surface engineering)

  • 제56권1호
  • /
  • Pages.84-93
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  • 2023
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  • 1225-8024(pISSN)
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  • 2288-8403(eISSN)
한국표면공학회 (The Korean Institute of Surface Engineering)
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SCALE-ORIGEN-ARP를 이용한 사용후핵연료 내 중성자 및 감마선원 분석

An analysis of neutron sources and gamma-ray in spent fuels using SCALE-ORIGEN-ARP

  • 차소희 (경희대학교 원자력공학과) ;
  • 박광헌 (경희대학교 원자력공학과)
  • So-Hee Cha (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kwang-Heon Park (Department of Nuclear Engineering, Kyung Hee University)
  • 투고 : 2022.11.21
  • 심사 : 2023.02.09
  • 발행 : 2023.02.28
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초록

The spent nuclear fuel is burned during the planned cycle in the plant and then generates elements such as actinide series, fission products, and plutonium with a long half-life. An 'interim storage' step is needed to manage the high radioactivity and heat emitted by nuclides until permanent-disposal. In the case of Korea, there is no space to dispose of high-level radioactive waste after use, so there is a need for a period of time using interim storage. Therefore, the intensity of neutrons and gamma-ray must be determined to ensure the integrity of spent nuclear fuel during interim storage. In particular, the most important thing in spent nuclear fuel is burnup evaluation, estimation of the source term of neutrons and gamma-ray is regarded as a reference measurement of the burnup evaluation. In this study, an analysis of spent nuclear fuel was conducted by setting up a virtual fuel burnup case based on CE16×16 fuel to check the total amount and spectrum of neutron, gamma radiation produced. The correlation between BU (burnup), IE (enrichment), and CT (cooling time) will be identified through spent nuclear fuel burnup calculation. In addition, the composition of nuclide inventory, actinide and fission products can be identified.

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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, I. C. Gauld, OrigenArp Primer: How to Perform Isotopic Depletion and Decay Calculations with SCALE/ORIGEN, ORNL/TM-2010/43, Oak Ridge National Lab, TN(USA) (2010)
  2. T. Makmal, O. Aviv, E. Gilad, A simple gamma spectrometry method for evaluation the burnup of MTR-type HEU fuel elements, Nucl. Instrum. Methods Phys. Res. A: Accel. Spectrom. Detect. Assoc. Equip., 834 (2016) 175-182. https://doi.org/10.1016/j.nima.2016.08.023
  3. S. K. Smith, Measurement of pressurized water reactor spent nuclear fuel rods by high-resolution gamma spectroscopy for burnup code verification, ORNL/SPR2017/535, ORNL, Oak Ridge, (1996) 14-19.
  4. S. M. Bowman, L. C. Leal, O. W. Hermann, C. V. Parks, ORIGEN-ARP, A fast and easy-to-use source term generation tool, J. Nucl. Sci. Technol., 37 (2000) 575-579. https://doi.org/10.1080/00223131.2000.10874953
  5. KHNP, Preliminary evaluation of spent fuel and defective fuel dry storage containers with high burn-up (2021)
  6. A. Favalli, Determining initial enrichment, burn-up, and cooling time of pressurizedwater-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Club interim-fuel storage facility in Sweden, NIM-A, 820, (2016) 102-111. https://doi.org/10.1016/j.nima.2016.02.072
  7. ORNL, Revised uranium-plutonium cycle PWR and BWR models for the ORIGEN computer code, ORNL/TM-6051, Oak Ridge National Lab, TN(USA) (1978)
  8. S. K. Smith, A. D. Nicholson, S. Croft, G. Nutter, High-resolution gamma spectroscopy measurements of pressurized water reactor spent nuclear fuel rods, ORNL/SPR-2017, Oak Ridge National Lab, TN(USA) (2018)