Nuclear Engineering and Technology

  • 제56권11호
  • /
  • Pages.4804-4812
  • /
  • 2024
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Evaluation of source terms using the BESNA code for reference spent fuels for future underground disposal system of South Korea

  • Kyu Jung Choi (Department of Nuclear Engineering, Hanyang University) ;
  • Duy Long Ta (Department of Nuclear Engineering, Hanyang University) ;
  • Shin Sung Oh (Department of Nuclear Engineering, Hanyang University) ;
  • Ser Gi Hong (Department of Nuclear Engineering, Hanyang University)
  • 투고 : 2024.03.13
  • 심사 : 2024.06.25
  • 발행 : 2024.11.25
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초록

In this work, the source-terms such as nuclide inventories, radioactivities, neutron and gamma spectra, and decay heats were evaluated using new code BESNA in which the burnup dependent one-group cross sections were evaluated based on MCNP6. This work started with the selection of the reference spent fuels through a statistical analysis of all the accumulated PWR spent fuels in South Korea for safety analysis of a geological repository, which led to the two reference spent fuels for each of 16x16 and 17x17 fuel assembly types considering representative low and high burnups. Finally, the source terms were evaluated using our inhouse code BESNA for the reference spent fuels, and they were compared with those from ORIGEN in SCALE6.2 for validation purposes. The results of the comparison showed that BESNA gives good agreements with ORIGEN for all the considered source terms.

키워드

과제정보

This work was supported by the Institute for Korea Spent Nuclear Fuel (iKSNF) and Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (Ministry of Trade, Industry and Energy (MOTIE)) (No. 2021040101003C), and supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Ministry of Trade, Industry and Energy (MOTIE) of Republic of Korea (No. RS-2024-00398867).

참고문헌

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