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A Study of Fracture Behavior of Spent Fuel in Long-Term Dry Storage
Sangil Choi,Sangsoon Cho,Seunghwan Yu 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.2
To investigate the mechanical integrity of spent nuclear fuel, the failure behavior of the cladding tube was examined under accident conditions. According to the SNL report, the failure behavior of cladding can be broadly classified into two types. The first is failure due to bending load caused by falling. The second is failure due to pinch load caused by space grid. In this study, mechanical integrity was evaluated through the stress intensity factor applied to the crack in failure behavior due to bending load. Since the exact value of the impact load due to fall was unknown, the load was applied by increasing the value up to 200 G in 20 G increments. The size of the crack is an important input variable, and 300 um was given by referring to the EPRI report, and the elastic modulus, a material property that determines the stress field, was given 75.22 GPa by referring to the FRAPCON code. Since the relationship between the direction of stress and the direction of the crack is also a major variable, simulations were conducted for both cracks perpendicular to and parallel to the stress direction. It was confirmed that at a load of 200 G, when the crack was parallel to the stress direction, stress concentration did not occur and had a very low stress intensity factor 0.01 ???√?. When perpendicular to the direction of stress, the stress intensity factor showed a value of 1 ???√?. However, considering that the critical value of the stress intensity factor due to hydride is 5 ???√?, it can be seen that perpendicular result also ensures the mechanical integrity of the cladding.
A Study of Mechanical Degradation Behavior of Spent Fuel in Long-term Dry Storage
Sangil Choi,Sangsoon Cho,Seunghwan Yu 한국방사성폐기물학회 2023 한국방사성폐기물학회 학술논문요약집 Vol.21 No.1
Research on the safety of nuclear spent fuel has been heavily experimented and modelled from a mechanical perspective. The issues of corrosion, irradiation creep, hydride and hydrogen embrittlement have been addressed more than two decades since the early 2000s. Among these degradation behavior, hydrogen embrittlement and hydride reorientation have been the most important topics for establishing the integrity of nuclear spent fuel and have been studied in depth. In order to assess the safety of spent nuclear fuel, firstly, it is necessary to establish the safety criteria in all nuclear cycle, i.e., the failure criteria guidelines for nuclear fuel assemblies and nuclear fuel rods, and then examine the safety analysis. The contents of U.S.NRC Regulations, Title 10 General, Chapter 1 Code of Federal Regulation (CFR), Part 50, 71 and 72, describe the safety criteria for the safety assessment of nuclear fuel assemblies and nuclear fuel rods. In this study, technically important points in safety analysis on nuclear fuel are checked through the reference of those NRC regulation. As result, we confirmed that the safety assessment of nuclear fuel after 20 years of interim storage is now being tested by ORNL and PNNL. There are not quantitative criteria related to material safety. However qualitative criteria which is dependent on environmentally condition describe the safety analysis. There is some literature study about DBTT, yield stress, ultimate tensile strength, flexural rigidity data. In FRAPCON code Modelling of yield strength and creep had been established, but radial hydride or hydride reorientation has not considered.
충격 및 바운스 특성 양상을 위한 HEV-Relay의 설계
고윤기(Younki Ko),조상순(Sangsoon Cho),허훈(Hoon Huh),이상엽(Sangyoeb Lee),박홍태(Hongtae Park),오일성(Ilsung Oh) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.11
A HEV-relay plays a significant role as a mechanical switch which determines the operation of a gasoline engine or an electric motor in a hybrid electric vehicle (HEV). The HEV-relay has critical two problems in the operating process. First, the unstable current can occur in the operating process of the HEV-relay due to the severe bounce between moving and fixed electrode. Second, noises occur due to impact between electrodes in HEV-relay. In this research, spring properties such as stiffness and initial compression force, and electrode shape are designed to reduce the bounce time and noises caused by impact between moving and fixed electrode. The operating process of HEV-relay is simulated using LS-DY□A3D as explicit finite element code. The optimum spring properties are determined using the response surface method (RSM) as the design methodology, and the electrode shape is newly designed through the modifying the stiffness of moving and fixed electrode.
윤형철(Yoon, Hyungchul),조상순(Cho, Sangsoon),강석주(Kang, Sukju),김진훈(Kim, Jinhoon),김경태(Kim, Kyongtae),고대권(Ko, Daekwun),이시훈(Lee, Sihun),한광춘(Han, Gwangchun) 한국신재생에너지학회 2011 한국신재생에너지학회 학술대회논문집 Vol.2011 No.05
1900년대 이후 산업발전에 따른 인구의 도시 집중화로 인한 하수량 증가에 따라 하수슬러지 발생량이 점차 증가하게 되면서 하수슬러지 처리에 관한 문제 등이 제기되기 시작하였다. 국내의 경우 2003년 하수슬러지의 매립이 금지된 후, 발생슬러지 대부분을 해양투기 등을 통해 처리하여왔다. 2009년 기준으로 국내에서 발생되는 하수슬러지량과 처리 분포를 살펴보면 전국 433개소 하수처리장에서 1일 평균 8,295톤(3,028천톤/년)이 발생되고 있으며, 이 중 47%가 해양투기 되고 있는 실정이다. 그러나 해양투기마저도 런던협약'96의정서 가입으로 2012년부터 금지됨에 따라 국내에서는 슬러지처리 및 재활용 방안과 관련한 연구개발이 활발히 진행되고 있는 중이다. 하수슬러지 처리 및 재활용기술의 경우 다양한 공법 등이 개발 중에 있으나 설비의 불안정 및 높은 투자비 등으로 인해 아직까지 상용화 된 설비 등은 많지 않은 실정이다. 이에 따라 본 연구에서는 POSCO 건설에서 개발한 슬러지 연료화 기술을 통해 생산된 슬러지 탄을 석탄 화력발전소 등에 석탄 보조연료로 활용할 수 있는 방안을 강구하여 상용화 가능한 혼소 기술을 개발하고자 하였다. 슬러지탄(발열량 3.000kcal 이상)을 석탄 화력발전소 보일러에 일정 비율로 혼소하여 슬러지탄의 품질평가, 중금속 용출시험 및 함량분석, 잔재물의 중금속 용출시험 등을 실시하였으며, 그 결과 모든 시험항목에서 연료화 관련 법적기준을 만족하는 것으로 나타났다. 슬러지탄을 화력발전소에 혼소하여 사용할 경우, 2012년부터 시행예정인 RPS(Renewable Portfolio Standard)법 대응 및 석탄사용량 저감 등을 통한 CO₂ 저감으로 저탄소 녹색성장의 자원순환사회를 구축하는 데 이바지 할 것으로 판단된다.