• Proceedings of the KAIS Fall Conference
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• 2011.12b
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• pp.631-634
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• 2011

항공기용 착륙장치의 완충기 충격흡수 성능은 해석 과정을 거쳐 예측한 값과 낙하시험을 수행하여 그 성능을 입증하여야 한다. 이는 미 연방 항공 규정에서 요구하고 있는 사항이다. 본 논문에서는 착륙장치 낙하시험을 위한 설비, 시험절차 및 시험방법과 낙하시험 수행 결과를 제시한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.543-548
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• 1996

이 연구의 목적은 고리 3/4호기 및 영광 1/2호기의 음의 중성자속 변화율에 의한 원자로 트립(NFRT) 설정치를 제거하여 불의의 제어봉 낙하 사고시에 원자로 트립을 방지하는 것이다. 현재의 인허가된 안전해석 방법론에 의하면 제어봉 낙하사고시에 NFRT에 의하여 원자로가 트립되고 결국 발전소의 이용율이 감소하게 되는데 본 연구에서 적용된 새로운 방법론으로는 이 NFRT 보호신호 없이도 제어봉 낙하사고시에 발전소의 안전성을 입증할 수 있다. 안전분석은 주기별로 다른 핵설계 자료 즉, 냉각재 온도상수, 전출력에서의 제어봉가 및 제어봉 삽입한계 등을 이용하여 수행되었다. 웨스팅하우스형 연료인 OFA 및 V5H에 대하여 고리 4호기 6주기외 3개 주기에 대하여 분석되었다. 분석된 주기들에 대해서 NFRT 신호 없이도 핵비등 이탈률(DNBR) 설계기준을 모두 만족하였다. 그러므로 고리 3/4호기 및 영광 1/2호기의 NFRT 신호는 제거할수 있고 이로써 제어봉 낙하사고시의 발전소 불시정지를 방지할수 있다.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.16 no.8
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• pp.5051-5059
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• 2015

Structural behaviour of the front loader for an agricultural tractor was analyzed for three impact test conditions: drop and catch, corner pull, and corner push. Rigid-body dynamic, transient structural, and static structural analyses were conducted using a commercial finite element software. Analysis of the drop and catch test dealt with the case that the bucket located at the maximum elevation was dropped and catched through three steps. Analysis of the corner pull test dealt with the case that the bucket constrained to the ground by a chain at its corner was raised suddenly. Analysis of the corner push test dealt with the case that the corner of the bucket collided with an obstacle. Results of analyses of the three test conditions showed that maximum stress occurs at the geometrically discontinuous location in the mount and is caused from local stress concentration. Results of the present research can be utilized as a guideline to achieve more reliable and safe structural design of the front loaders.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.3
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• pp.199-212
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• 2007

If a type IP-2 transport package were to be subjected to a free drop test and a penetration test under the normal conditions of transport, it should prevent a loss or dispersal of the radioactive contents and a more than 20% increase in the maximum radiation level at any external surface of the package. In this paper, we suggested the analytic method to evaluate the structural safety of a type IP-2 transport package using a thick steel plate for a structure part and a bolt for tying a bolt. Using an analysis a loss or dispersal of the radioactive contents and a loss of shielding integrity were confirmed for two kinds of type IP-2 transport packages to transport radioactive waste drums from a waste facility to a temporary storage site in a nuclear power plant. Under the free drop condition the maximum average stress at the bolts and the maximum opening displacement of a lid were compared with the tensile stress of a bolt and the steps in a lid, which were made to avoid a streaming radiation in the shielding path, to evaluate a loss or dispersal of radioactive waste contents. Also a loss of shielding integrity was evaluated using the maximum decrease in a shielding thickness. To verify the impact dynamic analysis for free drop test condition and evaluate experimentally the safety of two kinds of type IP-2 transport packages, free drop tests were conducted with various drop directions. For the tests we examined the failure of bolts and the deformation of flange to evaluate a loss or dispersal of radioactive material and measured the shielding thickness using a ultrasonic thickness gauge to assess a loss of shielding integrity. The strains and accelerations acquired from tests were compared with those by analyses to verify the impact dynamic analysis. The analytic results were larger than the those of test so that the analysis showed the conservative results. Finally, we evaluated the safety of the type IP-2 transport package under the stacking test condition using a finite element analysis. Under the stacking test condition, the maximum Tresca stress of the shielding material was 1/3 of the yielding stress. Two kinds of a type IP-2 transport package were safe for the free drop test condition and the stacking test condition.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.10 no.2
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• pp.105-115
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• 2012

Necessity of demonstration test to evaluate the structural integrity of a basket for accident conditions arose during license approval procedure for the WSPP's dry storage facility named MACSTOR/KN-400. A drop test facility for demonstration was constructed in KAERI site and demonstration tests for basket drop were conducted. As the upper welding region of a loaded basket was collided with a dropped basket during the drop test, the welding in this region was fractured and leakage happened after the drop test. The enhancement of basket design was needed since the existing basket design was not able to satisfy the performance requirement. The directions for design modification were determined and six enhanced designs were derived based on these directions. Structural analyses and specimen tests for each enhanced design were conducted. By evaluating structural analysis results and test results, one among six enhanced designs was decided as a final design for revision. The final design was the one to reduce the height of central post of a basket and to decrease the impact velocity with a dropped basket. Test basket models were fabricated with accordance with the final enhanced design. Additional demonstration test was performed for this test model and all the performance requirements were satisfied.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.32 no.2
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• pp.75-86
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• 2019

The biggest obstacle in the nuclear power generation is the high level radioactive waste such as the spent nuclear fuel. High level radioactivities and generated heat make the safe treatment of the spent nuclear fuel very difficult. Nowadays, the only treatment method is a deep geological disposal technology. This paper treats the structural safe design problem of the spent nuclear fuel disposal canister which is one of the core technologies of the deep geological disposal technology. Especially, this paper executed the nonlinear structural analysis for the stresses and deformations occurring in the canister due to the impulsive force applied to the spent nuclear fuel disposal canister in the case of an accidental drop and ground impact event from the transportation vehicle in the repository. The main content of the analysis is about that the impulsive force is obtained using the commercial rigid body dynamic analysis computer code, RecurDyn, and the stress and deformation caused by this impulsive force are obtained using the commercial finite element static structural analysis computer code, NISA. The analysis results show that large stresses and deformations may occur in the canister, especially in the rid or the bottom of the canister, due to the impulsive force occurring during the collision impact period.

• Journal of the Society of Naval Architects of Korea
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• v.54 no.2
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• pp.143-150
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• 2017

Previous methods to evaluate the risk of dropped objects rely on personnel experience of the engineer or operator without analyzed data. However analyzing historical statistic data is the best approach to find the safest operation route and to achieve more reasonable and reliable calculation results. By counting the failure frequency and fatal accident rate the risk can be quantified, and so controlled or mitigated with best economical risk reducing measures. This analysis gives a crane operator with useful information for selecting the best crane operation route, and a designer with an estimation of risk level for the dropped objects from a safety point of view.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.295-296
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• 2016

• Transactions of the Korean Society of Mechanical Engineers
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• v.8 no.4
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• pp.385-393
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• 1984

본 연구에서는 다트식 낙하충격 시험에 있어서 인성의 강소성 플라스틱 재료 의 준정적 선형의 점탄성 모델이 구성되어 해석되었다. 완화계수함수, E(t)=E$_{f}$ +(E$_{o}$ -E$_{f}$ )e$^{-t/tR}$ 형태의 점탄성 재료의 수정된 Maxwell요소모델을 근거 로 충격속도, 파괴에너지, 임계응력등의 중요변수들의 상대적 종속성이 근사계산으로 평가되었다.

• 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.