Journal of Radiation Protection and Research

The Korean Association for Radiation Protection (대한방사선방어학회)
권호 표지
DOI QR코드

DOI QR Code

A Comparative Study on Effective One-Group Cross-Sections of ORIGEN and FISPACT to Calculate Nuclide Inventory for Decommissioning Nuclear Power Plant

  • Cha, Gilyong (Research and Development Department, RADCORE Co. Ltd.) ;
  • Kim, Soonyoung (Research and Development Department, RADCORE Co. Ltd.) ;
  • Lee, Minhye (Research and Development Department, RADCORE Co. Ltd.) ;
  • Kim, Minchul (Central Research Institute, Korea Hydro & Nuclear Power Co. Ltd.) ;
  • Kim, Hyunmin (Central Research Institute, Korea Hydro & Nuclear Power Co. Ltd.)
  • Received : 2021.10.20
  • Accepted : 2022.01.14
  • Published : 2022.06.30
Download PDF
⟨ Previous Next ⟩

Abstract

Background: The radionuclide inventory calculation codes such as ORIGEN and FISPACT collapse neutron reaction libraries with energy spectra and generate an effective one-group cross-section. Since the nuclear cross-section data, energy group (g) structure, and other input details used by the two codes are different, there may be differences in each code's activation inventory calculation results. In this study, the calculation results of neutron-induced activation inventory using ORIGEN and FISPACT were compared and analyzed regarding radioactive waste classification and worker exposure during nuclear decommissioning. Materials and Methods: Two neutron spectra were used to obtain the comparison results: Watt fission spectrum and thermalized energy spectrum. The effective one-group cross-sections were generated for each type of energy group structure provided in ORIGEN and FISPACT. Then, the effective one-group cross-sections were analyzed by focusing on 59Ni, 63Ni, 94Nb, 60Co, 152Eu, and 154Eu, which are the main radionuclides of stainless steel, carbon steel, zircalloy, and concrete for decommissioning nuclear power plant (NPP). Results and Discussion: As a result of the analysis, 154Eu and 59Ni may be overestimated or underestimated depending on the code selection by up to 30%, because the cross-section library used for each code is different. When ORIGEN-44g, -49g, and -238g structures are selected, the differences of the calculation results of effective one-group cross-section according to group structure selection were less than 1% for the six nuclides applied in this study, and when FISPACT-69g, -172g, and -315g were applied, the difference was less than 1%, too. Conclusion: ORIGEN and FISPACT codes can be applied to activation calculations with their own built-in energy group structures for decommissioning NPP. Since the differences in calculation results may occur depending on the selection of codes and energy group structures, it is appropriate to properly select the energy group structure according to the accuracy required in the calculation and the characteristics of the problem.

Keywords

References

  1. United States Nuclear Regulatory Commission. Maine Yankee Decommissioning Experience Report: detailed experiences 1997-2004 [Internet]. Rockville, MD: United States Nuclear Regulatory Commission; 2012 [cited 2022 Mar 1]. Available from: https://www.nrc.gov/docs/ML1233/ML12338A389.pdf.
  2. International Atomic Energy Agency. Radiological characterization of shut down nuclear reactors for decommissioning purposes (Technical Report Series No. 389). Vienna, Austria: International Atomic Energy Agency; 1998.
  3. Los Alamos National Laboratory. MCNP6 User Manual version 6.1 [Internet]. Los Alamos, NM: Los Alamos National Laboratory; 2013 [cited 2022 Mar 1]. Available from: https://mcnp.lanl.gov/mcnp_manual.html.
  4. Rearden BT, Jessee MA. SCALE Code System version 6.2.3 (ORNL/TM-2005/39) [Internet]. Oak Ridge, TN: Oak Ridge National Laboratory; 2018 [cited 2022 Mar 1]. Available from: https://www.ornl.gov/sites/default/files/SCALE_6.2.3.pdf.
  5. OECD Nuclear Energy Agency. The JEFF-3.0 Nuclear Data Library. Paris, France: Organisation for Economic Co-operation and Development; 2005.
  6. Forrest RA. FISPACT-2007: user manual (UKAEA FUS 534) [Internet]. Oxfordshire, UK: United Kingdom Atomic Energy Authority; 2007 [cited 2022 Mar 1]. Available from: https://scientific-publications.ukaea.uk/wp-content/uploads/UKAEA-FUS534FINAL.pdf.
  7. Sublet JC, Packer LW, Kopecky J, Forrest RA, Koning AJ, Rochman DA. The European Activation File: EAF-2010 neutron-induced cross section library [Internet]. Oxfordshire, UK: Culham Centre for Fusion Energy; 2010 [cited 2022 Mar 1]. Available from: https://tendl.web.psi.ch/bib_rochman/EAF2010.pdf.
  8. Chadwick MB, Herman M, Oblozinsky P, Dunn ME, Danon Y, Kahler AC, et al. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data (Report No. LA-UR 11-05121) [Internet]. Los Alamos, NM: Los Alamos National Laboratory; 2011 [cited 2022 Mar 1]. Available from: https://t2.lanl.gov/nis/publications/Chadwick-LA-UR-11-05121.pdf.
  9. Meek T. Radiological site characterization plan for Trojan Nuclear Power Plant. Columbia County, OR: Trojan Nuclear Power Plant; 1995.