Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

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)
  • Received : 2024.03.13
  • Accepted : 2024.06.25
  • Published : 2024.11.25
Download PDF
⟨ Previous Next ⟩

Abstract

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.

Keywords

Acknowledgement

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).

References

  1. Ministry of Trade, Industry and Energy of South Korea, Workshop on the Spent Fuel Generation and Expectation of Spent Fuel Storage Saturation, February 10, 2023. 
  2. KETEP and KORAD, Workshop on the R &D Roadmap of High-Level Radioactive Waste, July 20, 2022. 
  3. D.L. Ta, S.G. Hong, D.S. Yook, A spent nuclear fuel source term calculation code BESNA with a new modified predictor-corrector scheme, Nucl. Eng. Technol. 54 (2022) 4722-4730.  https://doi.org/10.1016/j.net.2022.07.013
  4. M. Pusa, J. Leppanen, Computing the matrix exponential in burnup calculations, Nucl. Sci. Eng. 164 (2010) 140-150.  https://doi.org/10.13182/NSE09-14
  5. W.A. Wieselquist, The SCALE6.2 ORIGEN API for high performance depletion. International Conference on Mathematics and Computation (M&C2015), Nashville, TN, USA, 2015. 
  6. Los Alamos National Laboratory, MCNP6 User's Manual, LA-CP-13-00634, 2013. 
  7. W.L. Wilson, T.R. England, K.A. Van Riper, Status of CINDER'90 codes and data. Proceedings of the Fourth Workshop on Simulating Accelerator Radiation Environments (SARE4), Knowxville, 1998, pp. 14-16 September. 
  8. Ministry of Trade, Industry and Energy of South Korea, 10th Basic Electric Energy Supply Plan (2022~2036), January 13, 2023. 
  9. Posiva Oy, Safety Case for the Disposal of Spent Nuclear Fuel at Olkiluoto-Description of the Disposal System 2012, POSIVA 2015-05, December 2012. 
  10. M.D. DeHart, S.M. Bowman, Reactor physics methods and analysis capabilities in SCALE, Nucl. Technol. 174 (2011) 196-213.  https://doi.org/10.13182/NT174-196
  11. H.J. Choi, J.Y. Lee, J.W. Choi, Development of geological disposal systems for spent fuels and high-level radioactive wastes in Korea, Nucl. Eng. Technol. 45 (2013) 29-40. https://doi.org/10.5516/NET.06.2012.006