• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.7 no.1
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• pp.9-16
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• 2009

Transport package for radioactive material should be structurally safe under puncture drop condition and its safety should be verified by test and numerical analysis. Most finite element analyses for puncture drop have been performed without modeling the impact limiter since failure is occurred in the materials of the impact limiter. This paper presents a new modeling methodology, where an element is eroded in case that the material's failure criteria are reached at the element's integration point, to investigate the effect of the impact limiter in the puncture process. The effectiveness of the proposed scheme is shown through the puncture drop analysis of hotcell transport cask, which is under design in KAERI. The results show that about 80 percent of the total impact energy is absorbed due to the deformation of impact limiter. Using the present method the puncture drop can be analyzed more accurately, but it would give conservative results compared to the actual test condition.

• 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.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.3 no.3
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• pp.231-236
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• 2005

HIC transport packaging to transport a high integrity container(HIC) containing dry spent resin generated from nuclear power plants is to comply with the regulatory requirements of Korea and IAEA for Type B packaging due to the high radioactivity of the content, and to maintain the structural integrity under normal and accident conditions. It must withstand 9 m free drop impact onto an unyielding surface and 1 m drop impact onto a mild steel bar in a position causing maximum damage. For the conceptual design of a cylindrical HIC transport package, three dimensional dynamic structural analysis to ensure that the integrity of the package is maintained under all credible loads for 9 m free drop and 1 m puncture conditions were carried out using ABAQUS code.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.885-890
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• 1995

사용후핵연료 수송용기는 충돌사고에 대한 구조적 건전성을 입증하기 위하여 9 m 자유낙하조건에 대하여 수송용기의 충돌거동을 평가해야 한다. 본 연구의 목적은 수송용기가 9 m 높이에서 충돌면과 경사각을 갖고 충돌할 때의 동적거동을 파악하기 위한 것이다. 수송용기가 충돌과 함께 회전하며 연속충돌을 일으키는 45$^{\circ}$ 이하의 작은 경사각을 갖고 충돌할 매 수송용기에 발생하는 응력, 가속도, 충돌력 등을 분석하여 동적거동을 파악하였다. 또한, 수송용기의 경사각도를 변화시키며, 경사각도의 변화가 수송용기의 동적 거동에 미치는 영향을 파악하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.256-261
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• 1997

국내 원전의 사용후핵연료를 경제적으로 수송할 수 있는 대형 수송용기의 국내개발을 위하여 10년의 냉각기간을 갖는 28다발의 PWR 사용후핵연료를 수송할 수 있도록 기본 설계기준을 설정하였다. 이 대형 수송용기에 대하여 개념설계로부터 결정된 차폐두께와 칫수를 기준으로 기본구조를 결정하고 정상수송조건 및 가상사고 조건에 대한 구조해석을 수행하였다. 대형 수송용기는 내부에 많은 양의 PWR 사용후핵연료를 담고 있으므로 이들 핵연료의 중량은 구조설계에 큰 영향을 미치게 된다. 본 연구의 목적은 28다발의 PWR 핵연료를 담은 대형 수송용기가 9m 높이에서 자유낙하하여 충돌사고를 일으켰을 때의 안전성을 파악하기 위한 것이다. 수송용기가 충돌시 충격면에 발생하는 충격력으로 인한 충격완충체의 변형과 충격흡수, 수송용기에 발생하는 응력, 가속도, 충돌력 등의 동적거동을 파악하여 안전성을 입증하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.350-350
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• 2004

국내 사용후연료는 중간저장시설 확보가 지연됨에 따라 점차 각 발전소의 사용후연료 저장조가 포화상태에 이르고 있다. 국가정책에 따른 사용후연료 중간저장시설의 운영이 시작되는 시점까지 발전소에서 사용후연료 저장용기가 하나의 대안으로 고려될 수 있다. 경수로 사용후연료의 저장용기의 구조설계는 취급사고의 한 형태로서 낙하조건에 대한 안전성을 요구하고 있다. 경수로 사용후연료 24 다발을 적재하는 캐니스터는 콘크리트 외부용기(overpack)의 상부로부터 하향 방향으로 삽입된다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.2
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• pp.149-156
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• 2016

The spent fuel stored in the pool is vulnerable to external impacts, since the severe reactor conditions degrade the structural integrity of the fuel. Therefore an accident during shipping and handling should be considered. In an extreme case, the fuel assembly drop can be happened accidentally during handling the nuclear fuel in the spent fuel pool. The rod failure during such drop accident can be evaluated by calculating the impact force acting on the fuel assembly at the bottom of the spent fuel pool. The impact force can be evaluated with the impact velocity at the bottom of the spent fuel pool. Since fuel rods occupies most of weight and volume of a nuclear fuel assembly, the information of the rods are important to estimate the hydraulic resistance force. In this study, the hydraulic force acting on the $3{\times}3$ short rod bundle model during the drop accident is calculated, and the result is verified by comparing the numerical simulations. The methodology suggested by this study is expected to be useful for evaluating the integrity of the spent fuel.

• 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.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.18 no.1
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• pp.43-49
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• 2005

The package used to transport radioactive materials, which is called by the shipping cask, must be safe under normal and hypothetical accident conditions. These requirements for the cask design must be verified through test or finite element analysis. Since the cost for FE analysis is less than the one for test, the verification by FE analysis is mainly used. But due to the complexity of mechanical behaviors, the results depend on how users apply the codes and can cause severe errors during analysis. In this paper, finite element analysis is carried out for the 9 meters free drop condition of the hypothetical accident conditions using LS-DYNA3D and ABAQUS/Explicit. We have investigated the analyzing technique lot the free drop impact test of the cask and investigated several vulnerable cases. The analyzed results were compared with each other. We have suggested a reliable and relatively simple analysis technique for the drop test of spent nuclear fuel casks.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.312-317
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• 1998

사용 후 핵연료 수송용기는 자유낙하 충돌사고에 대비해 양 끝단에 충격완충체를 부착하는데 이 충격완충체의 층격흡수특성은 수송용기의 구조적 안전성애 크게 영향을 미친다. 충격완충체의 층격흡수재를 감싸주는 철제 케이스와, 내부 격막판의 용접 접합부는 제작공정상 일부 부분이 부분접합 형태를 갖기 때문에 완전 접합된 부분이나 모재인 판재 부분에 비해 강도가 약하다. 따라서, 본 연구에서는 충격완충체의 부분접합부와 같은 조건의 접합상태를 고려한 용접시편의 시험을 통해서 충격완충체 케이스의 용접 접합부에 대한 접합강도와 기계적 특성을 분석하고, 접합부의 강도특성이 수송용기의 자유낙하 충돌거동에 미치는 영향을 예측하였다.