• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.324-325
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• 2011

• Journal of Radiation Protection and Research
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• v.29 no.3
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• pp.157-163
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• 2004

Atmospheric dispersion modelling has been widely used to predict the fate and transport of radioactive or toxic materials released from nuclear facilities which is an unlikely accidental event. To improve the forecasting performance of the dispersion model, it is required that source rate and dispersion characteristics must be defined appropriately. Generally, source term of the radioactive materials is much uncertain at the early phase of an accidental event. In this study, we computed the source rate with the experimental field data monitored at the Yeoung-Kwang nuclear site and obtained the optimal source rate to minimize the errors between the measured concentrations and the computed ones by the Gaussian plume model. Computed source term showed a good result within 24% of the artificially released source rate.

• Proceedings of the Korean Institute of Navigation and Port Research Conference
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• 2022.11a
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• pp.154-154
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• 2022

2019년 9월 8일 자동차운반선 골든레이호가 미국 브런즈윅항(Brunswick)항에서 출항 도중 전도되는 사고를 입었다. 도선사와 선원 23명은 모두 구조되었으나, 사고선박은 복구 불가로 전손(해체)처리 되었다. 미연방교통안전위원회(NTSB)는 담당사관이 선박 복원성 계산 프로그램에 평형수 양을 잘못 입력하였고, 충분한 GM 부족으로 선회 중 발생한 경사모멘트에 대응하지 못해 전도된 것으로 추정하였다. 우리나라 중앙해양안전심판원의 특별조사부에서도 미국과 동일한 원인에 의해 전도된 것으로 판단하였다. 본 연구에서는 골든레이호와 유사한 선박을 대상으로 상황별 GM를 계산하였고, 상황별/속력별 최대 횡경사각을 계산하였다. 선속 10노트 이하에서는 GM값이 작은 상황에서도 전도 위험은 높지 않았다. 다만, 13노트 이상이 되면 20도 이상의 횡경사각이 발생하여 전도 위험이 높아짐을 알 수 있었다. 이번 골든레이호 전도사고와 같은 사고를 방지하기 위해서는 담당사관이 복원성 계산능력을 충분히 갖출 수 있도록 복원성에 대한 교육 및 훈련을 강화할 필요가 있으며, 복원성 계산과정에서 발생할 수 있는 오류를 확인하기 위한 검증 절차를 선박과 회사에서 마련할 필요가 있다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.368-376
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• 2004

The estimation of the diffusion coefficients of the Gaussian plume model and the release rate by assimilation of tracer-gas measurements on Younggwang site was tested. Diffusion coefficients were modified by linear programming of both the measurements and the simulated using the Gaussian plume model. The application of the modified diffusion coefficients improved the prediction ability of the Gaussian plume model on both 3 km and 8 km arc lines. And, the release rate of tracer gas was estimated using least squares method. The optimal source rate was estimated by minimizing the errors between the measured concentrations and the computed ones by the Gaussian plume model. The obtained release rate showed a good agreement with the real release rate of the Younggwang experiment in 24%.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.2
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• pp.155-162
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• 2008

Inventories to be disposed of, reference turnup, and source terms for CANDU spent fuel were evaluated for geological disposal system design. The historical and projected inventory by 2040 is expected to be 14,600 MtU under the condition of 30-year lifetime for unit 1 and 40-year lifetime for other units in Wolsong site. As a result of statistical analysis for discharge burnup of the spent fuels generated by 2007, average and stand deviation revealed 6,987 MWD/MtU and 1,167, respectively. From this result, the reference burnup was determined as 8,100 MWD/MtU which covers 84% of spent fuels in total. Source terms such as nuclide concentration for a long-term safety analysis, decay heat, thermo-mechanical analysis, and radiation intenity and spectrum was characterized by using ORIGEN-ARP containing conservativeness in the aspect of decay heat up to several thousand years. The results from this study will be useful for the design of storage and disposal facilities.

• Journal of Radiation Protection and Research
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• v.28 no.1
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• pp.1-8
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• 2003

The periodic safety review of operational nuclear power plants requires that the plants should keep a well organized environmental monitoring program. The past records of environment monitoring data were analyzed. and the tritium concentrations of the samples in the surface and ground water around Kori site were measured. It was shown that the tritium concentrations around the Kori site were slightly higher than that of natural background. The change of background tritium concentration was estimated through a numerical modeling. Two different versions of 7 compartments model - the world and the northern hemisphere - defined in NCRP-62 were modeled for the global tritium cycling. The numerical solution of the model was obtained using a computer program, AMBER. The four cases of tritium source-terms into the atmosphere were considered. The results showed that the tritium concentration in the surface soil water was higher than that in sea water or surface stream water. Also, it was shown that the tritium produced by the interaction between cosmic rays and the gases were the major source of tritium, and the tritium produced by nuclear weapon test decreased considerably.

• Journal of Radiation Protection and Research
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• v.38 no.4
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• pp.189-193
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• 2013

Annual dose on the containment building wall of the interim storage facility at normal condition was calculated to estimate the dose rate transition of the facility of PWR spent nuclear fuel. In this study, source term was generated by ORIGEN-ARP with 4.5 wt% initial enrichment, 45,000 MWd/MTU burnup and 10 years cooling time. Modeling of the storage facility and the containment building and radiation shielding evaluations were conducted by MCNP code depending on the distance between the wall and the facility in the building. In the case of the centralized storage system, the distance required for the annual dose rate limit from 10CFR72 was estimated to be 50 m.