Earticle

초록

영어

Background: The radionuclide inventory calculation codes such as ORIGEN and FISPACT collapse neutron reaction libraries with energy spectra and generate an effective one-group crosssection. 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.

목차

ABSTRACT
Introduction
Materials and Methods
1. Neutron Energy Spectrum
2. Computational Codes
3. Neutron Activated Nuclides of Interest
Results and Discussion
1. Comparison of Results from Each Computational Code
2. Comparison of Results using Various Energy Group Structures in Each Code
Conflict of Interest
Author Contribution
References

키워드

저자

• Gilyong Cha [ Research and Development Department, RADCORE Co. Ltd., Daejeon, Korea ]
• Soonyoung Kim [ Research and Development Department, RADCORE Co. Ltd., Daejeon, Korea ] Corresponding Author
• Minhye Lee [ Research and Development Department, RADCORE Co. Ltd., Daejeon, Korea ]
• Minchul Kim [ Central Research Institute, Korea Hydro & Nuclear Power Co. Ltd., Daejeon, Korea ]
• Hyunmin Kim [ Central Research Institute, Korea Hydro & Nuclear Power Co. Ltd., Daejeon, Korea ]

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 간행물명

  방사선방어학회지 [Journal of Radiation Protection and Research]

• 간기

  계간

• pISSN

  2508-1888

• 수록기간

  1976~2026

• 등재여부

  KCI 등재,SCOPUS

• 십진분류

  KDC 559 DDC 629