• 한국압력기기공학회 논문집
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• 제4권2호
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• pp.20-28
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• 2008

According to IAEA regulations, a transportation package of radioactive material should perform its intended function of containing the radioactive contents after the drop test, which is one of hypothetical accident conditions. Impact limiters attached to a transport cask absorb the most of impact energy. So, it is appreciated to determine properly the shape, size and material of impact limiters. A material data needed in this determination is a dynamic one. In this study, several materials considered as those of impact limiters were tested by a drop weight facility to acquire dynamic material characteristics data. Impact absorbing volume of the impact limiter was derived mathematically for each drop condition. A size optimization of impact limiter was conducted. The derived impact absorbing volumes were applied as constraints. These volumes should be less than critical volumes generated based on the dynamic material characteristics. The derived procedure to decide the shape of impact limiter can be useful at the preliminary design stage when the transportation package's outline is roughly determined and applied as input value.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.335-336
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.343-344
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• 2019

• 방사성폐기물학회지
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• 제20권2호
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• pp.133-149
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• 2022

The design of a wooden impact limiter equipped to a transportation cask for radioactive materials was optimized. According to International Atomic Energy Agency Safety Standards, 9 m drop tests should be performed on the transportation cask to evaluate its structural integrity in a hypothetical accident condition. For impact resistance, the size of the impact limiter should be properly determined for the impact limiter to absorb the impact energy and reduce the impact force. Therefore, the design parameters of the impact limiter were optimized to obtain a feasible optimal design. The design feasibility criteria were investigated, and several objectives were defined to obtain various design solutions. Furthermore, a probabilistic approach was introduced considering the uncertainties included in an engineering system. The uncertainty of material properties was assumed to be a random variable, and the probabilistic feasibility, based on the stochastic approach, was evaluated using reliability. Monte Carlo simulation was used to calculate the reliability to ensure a proper safety margin under the influence of uncertainties. The proposed methodology can provide a useful approach for the preliminary design of the impact limiter prior to the detailed design stage.

• 한국전산구조공학회논문집
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• 제18권3호
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• pp.245-254
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• 2005

방사성물질은 다양한 분야에서 사용되고 있으며 이에 따른 국내 및 국제간 운반이 계속적으로 증가하고 있다. 방사성물질을 수송하기 위해서는 수송용기의 안전성이 확보되어야 한다. 방사성물질 수송용기의 안전규정에 관해서는 국내 원자력법 운반안전규정 및 IAEA 운반규정에서 규정하고 있다. 방사성물질 수송용기 중에서 사용후핵연료를 운반하는 수송용기는 본체와 충격완충제로 구성되어 있다. 본 논문에서는 사용후핵연료 수송용기의 충격완충제에 작용하는 충격력을 계산하는 간편한 실험식을 차원해석을 통하여 유도하였다. 해석결과는 기존의 충격면적법 및 유한요소해석과 비교를 통하여 그 타당성을 입증하였다. 본 실험식을 이용하여 수송용기의 낙하충격력을 쉽게 예측할 수 있다.

• 방사성폐기물학회지
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• 제19권1호
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• pp.123-132
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• 2021

Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 ㎡ with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials' density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10-4 mSv·yr-1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.

• 방사성폐기물학회지
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• 제14권3호
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• pp.279-287
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• 2016

경주 중 저준위 방사성폐기물 처분시설의 운영에 따라, 한국원자력연구원(대전)에 임시보관 중인 방사성동위원소폐기물을 처분시설로 육상운반하였다. 본 연구에서는 방사성동위원소폐기물의 국내육상운반에 따른 작업자 및 일반인에 대한 방사선 피폭선량을 평가하고 그 결과를 국내 방사선피폭 법적제한치와 비교하였다. 또한 방사성폐기물의 상하차 작업 시 작업자와 드럼 간 거리 및 방사성핵종 누출율의 변화에 따른 예상피폭선량의 민감도를 분석하였다. 정상 및 사고조건에서의 예상피폭선량은 국내 법적제한치를 충분히 만족하였음을 확인하였다.

• 방사성폐기물학회지
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• 제20권1호
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• pp.13-22
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• 2022

The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술대회지
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• pp.289-289
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• 2004

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.100-101
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• 2018