Preliminary Estimation of Activation Products Inventory in Reactor Components for Kori unit 1 decommissioning

고리1호기 해체시의 원자로 구조물에서의 방사회 생성물 재고량 예비평가

  • Lee, Kyung-Jin (KOREA Hydro & Nuclear Power Co., Ltd (KHNP) Nuclear Environment Technology Institute (NETEC)) ;
  • Kim, Hak-Soo (KOREA Hydro & Nuclear Power Co., Ltd (KHNP) Nuclear Environment Technology Institute (NETEC)) ;
  • Sin, Sang-Woon (KOREA Hydro & Nuclear Power Co., Ltd (KHNP) Nuclear Environment Technology Institute (NETEC)) ;
  • Song, Myung-Jae (KOREA Hydro & Nuclear Power Co., Ltd (KHNP) Nuclear Environment Technology Institute (NETEC)) ;
  • Lee, Youn-Keun (Korea institute of Nuclear Safety (KINS))
  • 이경진 (한국수력원자력(주) 원자력환경기술원) ;
  • 김학수 (한국수력원자력(주) 원자력환경기술원) ;
  • 신상운 (한국수력원자력(주) 원자력환경기술원) ;
  • 송명재 (한국수력원자력(주) 원자력환경기술원) ;
  • 이윤근 (한국원자력안전기술원)
  • Published : 2003.06.30

Abstract

Based on the necessity to evaluate the activation products inventory during decommissioning lot domestic nuclear power plants, a preliminary estimation of the activation products inventory for Kori unit 1, which is getting close to the end of lifetime, was carried out with ANISN and ORIGEN2 code. In order to calculate neutron nux using ANISN code, the reactor was divided into 9 zones from core to bioshield concrete for radial direction. Also :he cross-section of main nuclides were calibrated with neutron flux in the reactor pressure vessel(RPV) region. The results showed that 95 % of tile total radioactivity in RPV from reactor shutdown to 10 years came from the nuclides of $^{55}Fe,\;^{59}Ni,\;^{63}Ni\;and\;^{60}Co$. And the total radioactivity with cooling of more than 50 years after decommissioning was no more than 0.2 % of at the time of shutdown. Considering the weight of RPV is 210 tons, the total radioactivity of RPV reached to $5.25{\times}10^{6}GBq$ at shutdown time. As compared with the total radioactivity of bioshield concrete at reactor shutdown time, the radioactivity after tooling more than 10 years was below 1 %.

본 연구에서는 최근 국내 원자력발전소의 해체시 방사화 생성물 재고량의 평가 필요성이 대두됨에 따라 원자로 수명종로가 가까워지고 있는 고리1호기를 대상으로 원자로 각 구조물의 방사라 생성물 재고량을 ANISN과 ORIGEN2 코드를 이용하여 예비평가를 수행하였다. 코드 입력자료로는 노심에서부터 차폐콘크리트까지 반경방향으로 8개 영역으로 나누어 ANISN 코드를 사용하여 중성자속을 계산하였다. 또한 압력용기의 중성자속 분포를 가지고 주요 핵종의 단일 그룹 반응단면 적을 보정하였다. 본 연구의 결과 압력용기의 경우 원자로 정지시점에서 약 10년까지는 $^{55}Fe,\;^{59}Ni,\;^{63}Ni,\;^{60}Co$ 핵종이 총 방사능의 약 95%정도를 차지하였으며, 약 50년 이상 냉각 후의 총 방사능은 원자로 정지시점과 비교하여 약 0.2 % 이하로 감소하는 것으로 평가되었다. 또한 압력용기의 무게가 210 ton임을 고려해 볼 때, 압력용기의 총 방사화생성물 재고량은 $5.25{\times}10^6GBq$로 계산되었다. 또한 차폐콘크리트의 경우 약 10년 이상 냉각 후의 총 방사능은 원자로 정지시점과 비교하여 1 %이하로 급격히 감소하는 것으로 평가되었다.

Keywords

References

  1. IAEA, 'Radiological characterization of shut down nuclear reactors for decommissioning purposes,' Technical Report Series No. 389 (1998)
  2. Markku Anttila, Frej Wasastjerna, 'Activity inventory of the activated decommissioning waste in the Olkiluoto nuclear power plant,' Nuclear Waste Commission of Finnish Power Company (1989)
  3. Allen G. Croff, 'A user's manual for the ORIGEN2 computer code, Oak Ridge National Laboratory Report,' ORNL/TM-7175 (1980)
  4. Allen G. Croff, 'ORIGEN2: A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials,' Nuclear technology, 62, 335-351 (1983)
  5. D. E. Robertson, C. W. Thomas, N. L. Wynhoff, D. C. Hetzer, 'Radionuclide Characterization of Reactor Decommissioning Waste and Spent Fuel Assembly Hardware,' NUREC/CR- 5343(1991)
  6. 한국 핵자료 연구회, http://atom.kaeri.re.kr/
  7. CCC-254/ANISN-ORNL, 'One-Dimensional Discrete Ordinate Transport Code System with Anisotropic Scattering,' ORNL, RSIC (1994)
  8. BUGLE96, 'Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications,' ORNL/DLC-185, RSIC(1999)
  9. Kim Jae Shik, Choi, Gyoo Hwan, 'The Nuclear Design and Core Physics Characteristics of the Kori Nuclear Power Plant Unit 1 Cyclel 9,' KNF-KIC19-00023, 한전원자력연료주식회사(2000)
  10. KORI unit 1 Final Safety Analysis Report Vol III, 한국전력공사 (1976)
  11. American National Standard for Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants, ANSL/ANS6.4(1997)