• 방사성폐기물학회지
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• 제14권4호
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• pp.411-422
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• 2016

최근 국내 원전의 경수로 사용후핵연료 습식 저장시설의 포화시점이 다가옴에 따라 운반 및 저장용기를 이용한 건식저장시스템 개발이 활발하게 수행되고 있다. 일반적으로 사용후핵연료 운반 및 저장용기 설계를 위한 차폐해석 시 장전 가능 연료 중 가장 보수적인 연료를 설계기준연료로 선정하여 해석을 수행한다. 그러나 실제 금속 운반용기에 장전되는 사용후핵연료는 해석평가에 적용된 설계기준연료에 한정되지 않고 다양하기 때문에 초기농축도, 연소도, 최소냉각기간의 특성을 고려한 차폐평가를 통하여 장전가능 여부가 결정된다. 이에 본 연구에서는 금속 겸용용기에 장전 가능한 연료를 대상으로 국내 운반기준을 만족하는 최소냉각기간의 결정을 위한 차폐해석 방법을 기술하였다. 특히 발생량이 많은 초기농축도 3.0~4.5wt%의 사용후핵연료는 차폐해석 구간을 세분화하여 평가하여 연구결과의 활용에 효율성을 높이고자 하였다. 차폐평가를 통해 2008년까지 국내 원전에서 발생한 장전대상연료 중 약 81%의 사용후 핵연료를 금속겸용용기로 운반할 수 있는것으로 평가되었다. 본 연구결과를 통해 금속 겸용용기의 운반조건에 장전 가능한 연료의 특성을 제시함으로써 운반 시 운영절차의 개발을 위한 기술적 근거 수립에 도움이 되고자 한다.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.427-438
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• 2013

In this paper we discuss spent fuel management options in the Republic of Korea (ROK) from two interrelated perspectives: Centralized dry cask storage and spent fuel pyroprocessing and burning in sodium fast reactors (SFRs). We argue that the ROK will run out of space for at-reactors spent fuel storage by about the year 2030 and will thus need to transition centralized dry cask storage. Pyroprocessing plant capacity, even if approved and successfully licensed and constructed by that time, will not suffice to handle all the spent fuel discharged annually. Hence centralized dry cask storage will be required even if the pyroprocessing option is successfully developed by 2030. Pyroprocessing is but an enabling technology on the path leading to fissile material recycling and burning in future SFRs. In this regard we discuss two SFR options under development in the U.S.: the Super Prism and the Travelling Wave Reactor (TWR). We note that the U.S. is further along in reactor development than the ROK. The ROK though has acquired more experience, recently in investigating fuel recycling options for SFRs. We thus call for two complementary joint R&D project to be conducted by U.S. and ROK scientists. One leading to the development of a demonstration centralized away-fromreactors spent fuel storage facility. The other involve further R&D on a combined SFR-fuel cycle complex based on the reactor and fuel cycle options discussed in the paper.

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 2005년도 춘계 학술발표회 논문집
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• pp.383-389
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• 2005

This research is to develop a seismic response analysis method for a spent fuel storage cask. FEM model is built for the test model of 1/8 scale spent fuel dry storage cask using available 3D contact conditions in ABAQUS/Explicit. Input load for this analysis os a seismic wave of El-centro earthquake, and the friction and damping coefficients in the analysis condition we obtained from the test result. Penalty and kinematic contact methods of ABAQUS are used for mechanical contact formulation. The analysis method was verified for rocking angle obtained by seismic response tests. The kinematic contact method with an adequate normal contact stiffness showed a good agreement with tests.

• Structural Engineering and Mechanics
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• 제75권2호
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• pp.239-246
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• 2020

In this paper, a novel analytical method, Max-Min Approach (MMA), has been presented and applied to consider the nonlinear vibration of dry cask storage systems. The nonlinear governing equation of the structure has been developed using the shell theory. The MMA results are compared with numerical solutions derived by Runge-Kutta's Method (RKM). The results indicate a satisfying agreement between MMA and numerical solutions. Parametric studies have been conducted on the nonlinear frequency of dry casks. The phase-plan of the problem is also presented and discussed. The proposed approach can potentially ca be extended to highly nonlinear problems.

• 방사성폐기물학회지
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• 제15권1호
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• pp.91-99
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• 2017

국내에서 개발중인 콘크리트 저장용기는 방사성 물질의 격납 건전성을 유지하기 위하여 내부에 캐니스터를 포함하고 있다. 본 논문에서는 콘크리트 저장용기 내부 캐니스터의 뚜껑 용접시, 용접시간 저감과 이에 따른 캐니스터 용접부의 구조적 건전성을 확보하기 위한 방안으로, 정상, 비정상 및 사고조건에서 캐니스터 용접부 균열을 진전시키는 하중에 의해 발생되는 균열 깊이를 분석하여, 용접부의 최대 허용결함깊이를 평가하였다. 정상, 비정상 및 사고조건에서의 구조해석은 범용 유한요소해석 프로그램인 ABAQUS를 사용하였으며, 허용결함깊이는 ASME B&PV Code Section XI에 따라 막응력과 조합하중에 대해 평가하였다. 평가결과 콘크리트 저장용기의 캐니스터 용접부의 허용결함깊이는 18.75 mm로 평가되었으며, 이는 NUREG-1536에서 권고하고 있는 임계결함깊이를 만족하고 있는 것으로 나타났다.

• 한국소성가공학회:학술대회논문집
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• 한국소성가공학회 2002년도 춘계학술대회 논문집
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• pp.98-102
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• 2002

As the nuclear power plant has been operated continuously and increased gradually, transportation and storage of spent fuel are seriously considered nowadays. The transportation cask which contains radioactive material needs to be inspected about structural safety. About safety verification, description of IAEA Safety Standards states that cask must withstand hypothetical accident conditions. In this paper, 9m free drop impact analysis was performed for transportation cask and impact limiter by using the finite element methods. Furthermore, we obtained the dynamic behavior of wood to as compared with safety test results, and verified the safety of transportation cask.

• Nuclear Engineering and Technology
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• 제48권2호
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• pp.505-517
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• 2016

The structural integrity of a dual-purpose metal cask currently under development by the Korea Radioactive Waste Agency (KORAD) was evaluated, through numerical simulations and a model test, under high-speed missile impact reflecting targeted aircraft crash conditions. The impact conditions were carefully chosen through a survey on accident cases and recommendations from literature. In the impact scenario, a missile flying horizontally hits the top side of the cask, which is freestanding on a concrete pad, with a velocity of 150 m/s. A simplified missile simulating a commercial aircraft engine was designed from an impact loade-time function available in literature. In the analyses, the dynamic behavior of the metal cask and the integrity of the containment boundary were assessed. The simulation results were compared with the test results for a 1:3 scale model. Although the dynamic behavior of the cask in the model test did not match exactly with the prediction from the numerical simulation, other structural responses, such as the acceleration and strain history during the impact, showed very good agreement. Moreover, the containment function of the cask survived the missile impact as expected from the numerical simulation. Thus, the procedure and methodology adopted in the structural numerical analyses were successfully validated.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 춘계학술논문요약집
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• pp.153-154
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• 2017

The thermal analysis of transportation and storage cask for SNF was conducted during short term loading operations for forced gas drying condition. The fuel cladding temperature in 6 regions of SNF in the cask during the short term loading operations for forced gas drying condition is shown in the Fig. 3. The thermal analysis results of calculated maximum cladding temperature in each process demonstrate that operating scenario of TFD in detailed design maintain well below the temperature limits of $400^{\circ}C$.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.624-634
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• 2016

Nuclear criticality safety analyses (NCSAs) considering burnup credit were performed for the GBC-32 cask. The used nuclear fuel assemblies (UNFAs) discharged from Hanbit Nuclear Power Plant Unit 3 Cycle 6 were loaded into the cask. Their axial burnup distributions and average discharge burnups were evaluated using the DeCART and Multi-purpose Analyzer for Static and Transient Effects of Reactors (MASTER) codes, and NCSAs were performed using SCALE 6.1/STandardized Analysis of Reactivity for Burnup Credit using SCALE (STARBUCS) and Monte Carlo N-Particle transport code, version 6 (MCNP 6). The axial burnup distributions were determined for 20 UNFAs with various initial enrichments and burnups, which were applied to the criticality analysis for the cask system. The UNFAs for 20- and 30-year cooling times were assumed to be stored in the cask. The criticality analyses indicated that $k_{eff}$ values for UNFAs with nonuniform axial burnup distributions were larger than those with a uniform distribution, that is, the end effects were positive but much smaller than those with the reference distribution. The axial burnup distributions for 20 UNFAs had shapes that were more symmetrical with a less steep gradient in the upper region than the reference ones of the United States Department of Energy. These differences in the axial burnup distributions resulted in a significant reduction in end effects compared with the reference.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.345-345
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• 2004

사용후핵연료 수송용기는 원자력발전소의 운영에 있어서 매우 중요한 구성요소의 하나로서 역할을 해왔으며, 근래에 들어서는 발전소 부지 또는 저장시설에서의 저장용기로 함께 사용되면서 그 숫자가 급속히 증가하고 있다. 아직 엄청난 양의 사용후핵연료가 발전소 내의 사용후핵연료 저장조와 같은 수조에 저장되어 있지만, 최근에는 사용후핵연료의 단기 또는 장기 저장을 위한 효과적인 수단으로 수송용기를 이용한 저장을 채택하는 국가가 계속 증가하고 있다. 사용후핵연료 수송용기의 운전 및 유지보수에 대한 오랜 기간의 경험에서 얻은 기술적 노하우는 저장용기의 운전 및 유지보수에도 잘 활용될 수 있을 것이다. 수송저장 겸용용기 및 다목적용 용기의 증가는 이러한 겸용용기의 운전 및 유지보수에 대한 국제적 표준화를 요구하고 있다. 이에 대한 노력의 일환으로 국제원자력기구에서는 이들 겸용 용기에 대한 설계요구사항들을 지침의 형태로 마련하고 있다.