• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.4
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• pp.391-402
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• 2017

The Korea Radioactive Waste Agency (KORAD) has developed a concrete cask for the dry storage of spent nuclear fuel that has been generated by domestic light-water reactors. During long-term storage of spent nuclear fuel in concrete casks kept in dry conditions, the integrity of the concrete cask and spent nuclear fuel must be maintained. In addition, the radiation dose rate must not exceed the storage facility's design standards. A suitable shielding design for radiation protection must be in place for the dry storage facilities of spent nuclear fuel under normal and accident conditions. Evaluation results show that the appropriate distance to the annual dose rate of 0.25 mSv for ordinary citizens is approximately 230 m. For a $2{\times}10$ arrangement within storage facilities, rollover accidents are assumed to have occurred while transferring one additional storage cask, with the bottom of the cask facing the controlled area boundary. The dose rates of 12.81 and 1.28 mSv were calculated at 100 m and 230 m from the outermost cask in the $2{\times}10$ arrangement. Therefore, a spent nuclear fuel concrete cask and storage facilities maintain radiological safety if the distance to the appropriately assessed controlled area boundary is ensured. In the future, the results of this study will be useful for the design and operation of nuclear power plant on-site storage or intermediate storage facilities based on the spent fuel management strategy.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05c
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• pp.470-475
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• 1996

사용후핵연료 장기 건식저장시 여러가지 저장조건에서 사용후핵연료 피복관 및 사용후핵연료 ($UO_2$)에 대한 장기 건전성을 종합적으로 평가할 수 있는 SIECO 코드를 개발하였다. 건식저장 시스템은 사용후핵연료를 헬륨 및 공기분위기하에서 TN-24P 건식 저장용기에 장기 저장할 경우로 하였으며 피복관의 최대 표면온도는 COBRA-SFS코드를 사용하여 계산하였고, 열유동 해석결과를 바탕으로 SIECO코드를 이용하여 핵연료 연소도 및 냉각기간, 냉각매체에 따른 최대 건식저장 허용온도를 피복관의 열화 및 $UO_2$ 산화의 관점에서 계산하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.436-436
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• 2004

사용후 연료 건식 저장 용기가 낙하, 토네이도, 미사일, 홍수 및 지진으로 인한 사고에 대하여 전복이 발생되었을 때 강체 평면과 충돌에 의한 충돌 하중시의 구조 응력 평가하였다. 이를 위해 저장 용기의 무게 중심이 한계를 넘었을 때의 초기 전복 시작각을 무게 중심을 계산을 통해 구하였다. 상용 코드를 사용하여 전복 응력 해석 수행시 저장 용기의 강체 운동에 의하여 계산 시간이 길어지는 데, 이런 계산 시간을 줄이기 위해 일차 충돌 직전까지의 모델의 속도와 각속도 계산식을 이론적인 방법으로 구하여 해석 초기 조건으로 사용하는 방법에 대하여 제안하였다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.11 no.4
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• pp.333-349
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• 2013

As the capacity of spent nuclear fuel storage pool at reactor sites becomes saturated in ten years, long term dry storage strategy has been recently discussed as an alternative option in Korea. In this study, we reviewed safety-criteria-related research results on spent nuclear fuel performance and integrity under long-term dry storage and proposed the direction and the scope of future domestic research and development. Creep and hydride effect in relation to the embrittlement are known to be the major degradation mechanisms of the spent fuels during the long term dry storage. However, recent research results showed that hydride reorientation and hydride embrittlement are one of the most critical factors to the spent fuel integrity. Accordingly safety criteria of US and Japan for the storage system are basically founded on those mechanisms. However, in Korea, not only in-pile but out-of-pile experimental data have not been generated to understand fuel cladding degradation and to determine the criteria to ensure the safety. In addition, the transient behavior of the spent fuel during transportation also needs to be thoroughly examined. Therefore, various experimental research and development will be required to establish our own safety criteria for future long-term dry storage of domestic spent fuels.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.2
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• pp.139-152
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• 2006

A spent fuel storage cask is required to prove the safety of a canister under a hypothetical accidental drop condition. A hypothetical accidental drop condition means that a canister is assumed to be a lee drop on to a pad of the storage cask during loading it into a storage cask. A pad of the storage cask absorbs shock to maintain the structural integrities of a canister under a hypothetical accidental drop condition. In this paper a finite element analysis for various pad structures was carried out to improve the structural integrity of a canister under a hypothetical accidental drop condition. A pad of a storage cask was designed a steel structure with concrete. The 1/4 height of a pad was modified with a structure composed of a steel and a polyurethane foam as a impact limiter. The effect of a shape of a steel structure was studied. The effects of the thickness of a steel structure and the density of a polyurethane foam was also studied.

• Horticultural Science & Technology
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• v.17 no.6
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• pp.762-764
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• 1999

This experiment was conducted to investigate the effect of pretreatments and storage conditions on quality and vase life of cut 'Red Sandra' rose (Rosa hybrida L.). 'Red Sandra' rose flowers were harvested and pulsed with distilled water, 0.2% RVB or 200ppm aluminum sulfate+3% sucrose+50ppm $AgNO_3$+0.1mM ethionine for 22 hours and then stored in wet or dry condition for 12, 24, 48 hours at low or room temperature. Pulsing with aluminum sulfate+sucrose+$AgNO_3$+ethionine delayed bent-neck, increased solution absorption and flower diameter, and prolonged vase life rather than pulsing with distilled water or RVB. Storage in wet condition or low temperature also delayed bent-neck, increased solution absorption and flower diameter, and prolonged vase life compared with storage in dry or room temperature condition. As the storage hours prolonged, solution absorption, flower diameter, and vase life were decreased especially pulsing with distilled water. Pulsing with aluminum sulfate+sucrose+$AgNO_3$+ethionine prolonged vase life compared to pulsing with distilled water or RVB regardless of storage conditions and shipping hours.

• Journal of the Korea institute for structural maintenance and inspection
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• v.9 no.2
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• pp.95-102
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• 2005

Delaying and objection for the construction of storage spent-fuel disposal has prompted to consider expanding on-site storage of spent reactor fuel since it can eliminate the need for costly and difficult shipping and control of the spent fuel completely under the direction of the owner-utility. The dry storage unit developed in Canada can accommodate Korea heavy water reactor fuel elements and become a candidate for the Korean market. In this paper, finite element analysis were carried out in order to investigate the structural behavior of the nuclear spent fuel dry storage system, which is subjected to impact loads such as collision of a truck load and dropping of flask under the irregular operation.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.475-476
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• 2009

CFD 방법을 이용하여 건식저장 용기내 사용후핵연료 열전달 해석을 수행한 결과 연료봉의 붕괴열에 의한 내부 유체의 자연대류 현상과 상세 핵연료 온도분포를 예측할 수 있음을 확인하였다. 향후에는 다양한 시험조건에서 복사열전달을 포함한 정밀한 CFD 계산을 수행하여 피복관 온도분포의 예측치를 실험결과와 비교할 예정이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.05a
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• pp.79-80
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• 2016

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2011.10a
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• pp.507-508
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• 2011