• Title, Summary, Keyword: Activation products inventory

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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;Kim, Hak-Soo;Sin, Sang-Woon;Song, Myung-Jae;Lee, Youn-Keun
    • Journal of Radiation Protection and Research
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    • v.28 no.2
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    • pp.109-116
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    • 2003
  • 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 %.

Monte carlo estimation of activation products induced in concrete shielding around electron linac used in an X-ray container inspection system (X-ray 컨테이너 화물검색시스템의 전자선형가속기 주변 콘크리트 차폐벽 내 방사화생성물에 대한 몬테카를로법 평가)

  • Cho, Young-Ho
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.11 no.3
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    • pp.1035-1039
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    • 2010
  • Activation products generated by photoneutrons in concrete shielding wall around electron linac were estimated for a high energy X-ray container cargo inspection system. Monte carlo code, MCNPX2.5.0 was used for reference system of 9MeV fixed type dual-direction container cargo inspection system installed at major harbors in Korea. Activation products inventory generated by photoneutron (n,$\gamma$) reaction are estimated, and then radiation dose rate is calculated from the results.

A Study on Radioactive Source-term Assessment Method for Decommissioning PWR Primary System (PWR 1차계통내 해체 방사성선원항 평가방법에 관한 연구)

  • Song, Jong Soon;Kim, Hyun-Min;Lee, Sang-Heon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.2
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    • pp.153-164
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    • 2014
  • Currently, there are many programs which are now being developed or already developed to predict radionuclide and corrosion product at the stage of designing NPP. However, since there are not many developments in evaluating quantity of activation corrosion products occurring when disassembling a nuclear power plant there exist some difficulties in calculating accurately. In order to evaluate activation products inventory for the research of effect of neutron activation in the reactor vessel, component of nuclear reactor and adjacent structures, it should be evaluated by using operation history of nuclear reactor, material composition of structure and average neutron flux in every field representing fixed structure of nuclear reactor. In this study, CORA, PACTOLE, CRUDSIM, CREAT and ACE codes are analyzed to predict the quantity of radionuclide and corrosion product of primary reactor which is used at the stage of designing. As a future study, the accuracy in calculating the quantity of product corrosion can be increase by finding out the possibility of use and improvement for evaluation of the decontamination.

Estimation of Radioactive Inventory for a major component of Reactor in Decommissioning (해체시 원자로 주요 구성품에 대한 방사능 재고량 평가)

  • Hak-Soo Kim;Ki-Doo Kang;Kyoung-Doek Kim;Chan-Woo Jeong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.2 no.1
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    • pp.69-75
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    • 2004
  • DORT and ORIGEN2 code were used for calculation of neutron flux and inventory in reactor pressure vessel(RPV) of Kori unit-1, To calculate neutron flux using DORT code, the reactor was divided into 94 mesh from the center of core to RPV and from 0 to 45 degree along the azimuth. The cross-sections of main nuclides were recalculated using neutron flux in the RPV region. The results showed that 95% of the total activity in RPV came from the nuclides of $^{55}$ Fe, $^{60}$ Co, $^{59}$ Ni and $^{63}$ Ni. And the total activity 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 initial total activity of RPV reached 5.25${\times}$10$^{6}$ GBq. To verify results of ORIGEN2 calculation, comparison between calculated and measured value at RPV of Kori unit-1 was peformed. The comparison results showed a good agreement.

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