• Journal of Energy Engineering
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• v.5 no.1
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• pp.19-27
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• 1996

Self-pressurization of cylindrical container of cryogen is numerically analyzed. The container is axi-symmetric and heated from side wall with constant heat flux. Natural convection by external heat flux is studied numerically using finite difference method. Oxygen, nytrogen and hydrogen are working fluids in this paper. Liquid is considered incompressible fluid and vapor is assumed to behave as gas meeting with virial equation of gas. The Second virial coefficients of gas are obtained from Lennard-jones model. The important variables which have effects on self-pressurization are external heat flux, heat capacity of wall and initial ullage in container. The most important variable of them is external heat flux. The pressure rise calculated from the virial gas model is slightly different from that calculated using Ideal gas model for oxygen.

• 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 Radiation Protection and Research
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• v.21 no.4
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• pp.313-327
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• 1996

As an at-reactor(AR) storage method o( spent fuel, there are horizontal concrete module type, metal storage cask type, concrete storage cask type, dual purpose (transportation and storage) cask type and multi-purpose (transportation, storage and disposal) cask type. All other types except multi-purpose one have been already used for AR dry storage of spent fuels after obtaining operation license in various foreign countries. Also the development of multi-purpose type has been continued for operation license. In America, Japan, Germany, Canada, Spain, Switzerland, and Czech Republic, etc., AR dry storage facilities are under operation or on propulsion, and spent fuels are transported to interim storage facility or reprocessing plant after dry storage at reactor temporarily. At Wolsung site, in case of Korea, concrete silo type has already been introduced, and it is believed to be inevitable to store spent fuels at reactor temporarily, considering the reality that storage capacity of spent fuel is approaching to the limit in some nuclear power plants. In this report, the system characteristics, design requirements, technical standards and status of AR storage system, which is suitable for domestic site such as Kori, have been studied. In most cases, the licensed period of storage cask is limited up to 20 years and the integrity of material and maintenance of leaktightness are required during the whole service life.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.2
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• pp.155-169
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• 2007

A transport container for a 500 kCi tritium storage vessel was developed, which could be used for the transport of metal tritide from Wolsong TRF facility to a disposal site. The structural, thermal, shielding, and confinement analyses were performed for the container in a view of Type B. As a result of structural analysis, the developed container sustained its integrity under normal and accidental conditions. The maximum temperature increase of the inner storage vessel by radiation was evaluated at $134.8^{\circ}C at room temperature. In $800^{\circ}C$ fire test, The thermal barrier of container sustained the inner vessel at $405^{\circ}C after 30 min, which temperature was allowable for the container integrity since maximum design temperature of inner vessel was $550^{\circ}C. In the evaluation of the shielding, the activity of radiation was nearly zero on the outer surface of inner vessel. Consequently the transport container for a 500 kCi tritium was evaluated to pass all the safety tests including accidental condition, so it was concluded that the designed transport container is proper to be used.

• Proceedings of the Korean Society of Food and Cookery Science Conference
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• 2003.10a
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• pp.85-85
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• 2003

저장용기(알루미나, 바이오, 스텐레스, 플라스틱)에 따른 김치의 품질특성을 구명하고자 4$^{\circ}C$+1에 31일간 저장하면서 pH, 산도, 환원당, 염도, 유산균, 관능평가 및 조직감등을 비교, 조사하였다. 저장기간에 따른 김치의 pH, 산도의 변화는 알루미나 용기에서 가장 적었고 플라스틱 용기에서 가장 크게 나타났다. 환원당의 경우 저장초기 22.65$\pm$0.04 mg/mL 이었고 저장후기에는 알루미나가 11.18$\pm$0.15$^{a}$ mg/mL이었고, 스텐레스, 바이오, 플라스틱이 각각 5.39$\pm$0.02$^{b}$ , 3.74$\pm$0.$10^{c}$ , 3.14$\pm$0.05$^{d}$ 이었다. (중략)

• Transactions of the Korean Society of Mechanical Engineers A
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• v.37 no.4
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• pp.547-554
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• 2013

The fuel storage vessel installed in CNG vehicles can be largely divided into 3 parts: head, cylinder, and dome. Studies of the cylinder and dome parts have already been performed, but sufficient design data is not available about the head part. Therefore, expert field engineers heavily depend upon trial-and-error methods. Therefore, FE analysis is performed to review the hot spinning process for forming the head part of the CNG vessel using the Arbitrary Lagrangian-Eulerian (ALE) method. The effects of forming factors on the load were analyzed. The values of the factors were chosen to avoid defects in the head part and buckling, and the forming feasibility of the head part was investigated. Furthermore, a bursting test was performed to evaluate the safety of the storage vessel.

• 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 the Korean Institute of Gas
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• v.27 no.2
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• pp.95-103
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• 2023

In this paper, in order to evaluate the deformation characteristics of the hydrogen gas storage vessel(Type 1) when considering gas pressure, the VMS generated in the hydrogen gas storage vessel according to the notch shape of ISO 18119 was interpreted as a FEM(Finite Element Method). According to the analysis results, the maximum VMS generated in the longitudinal notch was higher than the transverse notch. In addition, the stress of the storage vessel was analyzed by the stress ratio, which is the yield strength ratio of the material to the VMS generated. According to the analysis results, in the case of a storage vessel with a notch formed in the longitudinal direction, the inside and outside of the storage vessel increased to 0.85 and 0.50 at a gas pressure of 50 MPa, respectively, but were analyzed to be lower than 1.

• 한국신재생에너지학회:학술대회논문집
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• 2010.11a
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• pp.112.2-112.2
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• 2010

지구의 온난화로 인한 기상변화 등이 계속적으로 발생하는 가운데 전 세계는 지구 온난화의 가장 근본적인 원인인 이산화탄소의 방출을 줄이기 위한 방안을 찾기 위해 많은 노력을 하고 있다. 이에 대해 전 세계적으로 각종의 기후협약 체결, 리우선언, 도쿄의정서 등을 통해 온실가스 배출원인인 석유 등 화석에너지 배출을 억제하기 위한 활동이 행해지고 있으며, 기존의 화석연료를 대체할 수 있는 새로운 에너지를 발견하기 위한 연구개발에도 박차를 가하고 있다. 이러한 계속적인 연구개발에서, 세계의 국가들은 친환경 에너지인 태양열, 풍력, 지열 및 수소에너지와 같이 화석연료를 대체할 수 있는 다양한 에너지를 조사하고 개발해왔고 현재도 가장 적합한 에너지 자원을 찾기 위하여 노력 중에 있다. 최근에, 수많은 대체에너지 중 수소 에너지는 유해배출가스가 없기 때문에 가장 유망한 대안이라고 판단되어 전 세계가 수소에너지 연구개발에 주목하고 있다. 이러한 수소에너지를 교통수단에 적용하기 위하여 전 세계적으로 안전성 및 기술 확보를 위한 기술개발과 안전기준의 확립하기 위해 노력하고 있다. 현재 기술적으로 수소를 자동차용 연료로 사용하기 위해서는 수소를 액체 상태 및 압축 상태로 저장하는 것이다. 두 가지 저장방법 중 세계 대부분의 자동차 메이커들은 수소를 압축하는 방식을 채택하고 있으며, 자동차의 주행거리를 최대한 확보하기 위하여 수소가스를 고압으로 압축한 상태로 저장하는 방식을 사용하고 있다. 이에 따라 고압의 수소를 안전하게 저장할 수 있는 고압수소용기의 개발이 필요하다. 수소연료전지 자동차에 장착이 가능한 고압으로 압축된 수소를 저장할 수 있고, 자동차에 탑재할 수 있도록 적합한 크기의 가벼운 용기의 개발이 진행되어지고 있다. 자동차용 용기는 크게 4가지 타입으로 구분지어 진다. 현재는 4가지 타입의 압축용기 중 안전성과 중량을 만족시키기 위해 Type3와 Type4 형태의 용기가 수소자동차에 시범적으로 적용되어 운용되고 있다. 또한 고압수소용기의 신뢰성과 안전성을 확보하기 위한 기준 및 코드가 국 내외에서 연구 개발되고 있다. 본 연구에서는 수소연료전지자동차에 장착되는 고압수소용기의 국제기준 동향에 따른 국내의 차량용 고압수소용기를 위한 KGS 안전기준의 개발현황과 개발방향을 제시하고자 한다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.2
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• pp.271-279
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• 2018

During the seven years from 2009 to 2016, PWR SNF (spent nuclear fuel) transportation and storage systems suitable for domestic conditions were developed by the government to cope with the saturation of wet storage capacity in NPPs. One of the developed systems is a multipurpose metal cask applicable for transportation/storage; the other is a concrete cask dedicated to storage. Efficient cask technologies were secured utilizing the characteristics and experience of relevant industrial, academic and research institutes. Technological independence was also achieved through several patent registrations of research outcomes. To prepare for a rapid increase of demand in the near future, technology transfer of secured patents and technologies to the domestic industry was carried out twice in the years of 2016 and 2017.