• 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 the Korean Institute of Gas
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• v.18 no.5
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• pp.6-11
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• 2014

To optimize the design of fuel cylinder for LNG vehicles, we introduced the design parameters of the inner and the outer tank of the vessel support structure by analyzing the structural characteristics of conventional design. We selected the inner and outer diameter of the hollow support bars and a dimension of the inner structure of the vessel among the design parameters for design optimization. In this study the temperature distribution and thermal stress of the support structure were evaluated by using the utility program as MSC/MARC. The evaluation criteria are first mode natural frequency, total transferred energy through support structure and thermal stress. The developed design satisfied the design criteria and it was made of prototype. The prototype was verified through three-dimensional vibration testing and thermal performance test.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.11a
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• pp.87-88
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• 2006

사용후 핵연료용 수송용기의 설계 안전평가에서는 이제까지 용기에 수납되는 연료는 미조사, 즉 신연료라 가정해서 보수적으로 임계안전설계를 수행하여 왔다. 이것은 연소에 따른 연료내의 핵연료 물질의 감손 및 생성의 의한 반응도의 변동을 계산 평가하는 것이나 또는 연소로 인해 생성되는 중성자 흡수 핵종의 조성 및 함유량 등을 정확히 계산 평가하는 것이 복잡해서 곤란했던 것으로 그 요인을 들 수 있다. 사용 후 핵연료를 신 연료로 가정하는 등의 불합리성을 해소하고, 안전성을 잃지 않고 사용 후 핵연료 운반용기 들의 경제성을 추구하는 기운이 높아지고, 관련 연구가 적극적으로 진척되게 되었다. 그 결과 연소에 따른 연료내의 핵연료 물질의 감손 생성과 핵분열 생성물 등에 의한 반응도의 저하, 즉 중성자 실효 증배율의 저하를 고려한 것을 사용 후 핵연료용 캐스크 설계 안전평가에 취할 수 있게 되었다. 연소도 크레디트를 채용함으로서 사용후 핵연료내의 핵연료물질량은 실제로 존재하는 양을 사용하는 것이 되므로 초기 농축도가 높은 고연소도 연료에서 그 효과가 보다 크게 될 것이다. 이것은 연소도 크레디트 채용에 따라 연료 바스켓의 중성자흡수제 사용량 감소가 가능해져 사용 캐스크의 수를 줄일 수 있어 경제성 향상이 기대되고 아울러 그이 취급 횟수 및 수송횟수가 감소됨에 따라 안전성의 향상도 기대된다.

• 한국전기화학회:학술대회논문집
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• 2005.07a
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• pp.201-206
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• 2005

본 연구는 기 개발 완료된 천연가스차량용 200bar급 Type 3 복합재 압력용기를 개발로 축척된 핵심요소기술과 실질적인 경험을 바탕으로 수소연료전지 차량에 탑재할 350bar급 Type 3 복합재 압력용기에 대한 설계/해석과 시험평가의 핵심적인 사항을 고찰하였다. 설계/해석에는 350bar급 Type 3 복합재 압력용기에 대한 3차원 비선형 유한요소 모델링 및 해석기법이 제시되었고, 설계된 라이너형상과 와인딩 패턴을 이용하여 필라멘트 와인딩 공법으로 1차시제품을 제작하였다. 제작된 시제품에 대하여 파열시험 및 반복피로시험을 수행하여 설계/해석 기법의 타당성을 검증하였다.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.4
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• pp.411-422
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• 2016

Recently, because the wet pool storage facilities of NPPs in Korea has become saturated, there has been much active R&D on an interim dry storage system using a transportation and storage cask. Generally, the shielding evaluation for the design of a spent fuel transportation and storage cask is performed by the design basis fuel, which selects the most conservative fuel among the fuels to be loaded into the cask. However, the loading of actual spent fuel into the transportation metal cask is not limited to the design basis fuel used in the shielding evaluation; the loading feasibility of actual spent fuel is determined by the shielding evaluation that considers the characteristics of the initial enrichment, the maximum burnup and the minimum cooling period. This study describes a shielding analysis method for determining the minimum cooling period of spent fuel that meets the domestic transportation standard of the dual purpose metal cask. In particular, the spent fuel of 3.0~4.5wt% initial enrichment, which has a large amount of release, was evaluated by segmented shielding calculations for efficient improvement of the results. The shielding evaluation revealed that about 81% of generated spent fuel from the domestic nuclear power plants until 2008 could be transported by the dual purpose metal cask. The results of this study will be helpful in establishing a technical basis for developing operating procedures for transportation of the dual purpose metal cask.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.18 no.1
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• pp.65-71
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• 2019

The development of adsorbed natural gas (ANG) has emerged as one of potential solutions. It is desirable to reduce the weight of vessel by applying light-weighed a composite carbon fiber in order to response to a egulation of $CO_2$ emission. Through understanding of a composite carbon fiber, and material characteristic of a composite carbon fiber is required in order for better application of a reduction of weight and an analysis of material characteristic. Herein, this study suggest the composite carbon fiber vessel applied to the characteristic of carbon fiber, and it decides the preliminary shape based on the test of material characteristic for ANG vessel applied to a composite carbon fiber, and its basic shape calculate through on the netting theory. Moreover, the detail shape design is analyzed by a finite element analysis, and in the stage of detail sahp design and analysis of stress was performed on the typical shape using a finite element analysis, and the result of preliminary design was verified.

• Journal of the Korean Institute of Gas
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• v.15 no.1
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• pp.30-34
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• 2011

This paper presents a strength safety evaluation of composite pressure container for hydrogen fuel tanks with a storage capacity of 104 liter and 70MPa pressure. The carbon fiber composite container is manufactured by an aluminum liner of Al6061-T6 and composite multi-layers of hoop winding layer in circumferential direction, $12^{\circ}C$ inclined winding layer and $70^{\circ}C$winding layer in helical direction respectively. The FEM results on the strength safety of composite fuel tanks were evaluated with a criterion of design safety of US DOT-CFFC and KS B ISO 11119-2 codes. The FEM computed results indicate that the proposed design model of 104 liter composite container is safe based on two strength safety codes. But, the computed results of carbon fiber fuel tanks based on US DOT-CFFC code is safer compared with that of KS B ISO 11119-2. Thus the hydrogen gas pressure container of 70MPa may be evaluated and designed by US DOT-CFFC code for more strength safety.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.17 no.4
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• pp.375-387
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• 2019

In this study, the radiation dose rates for the design basis fuel of 360 assemblies CANDU spent nuclear fuel transportation cask were evaluated, by measuring radiation source terms for the design basis fuel of a pressurized heavy water reactor. Additionally, radiological safety evaluation was carried out and the validity of the results was determined by radiological technical standards. To select the design basis fuel, which was the radiation source term for the spent fuel transportation cask, the design basis fuels from two spent fuel storage facilities were stored in a spent fuel transportation cask operating in Wolsung NPP. The design basis fuel for each transportation and storage system was based on the burnup of spent fuel, minimum cooling period, and time of transportation to the intermediate storage facility. A burnup of 7,800 MWD/MTU and a minimum cooling period of 6 years were set as the design basis fuel. The radiation source terms of the design basis fuel were evaluated using the ORIGEN-ARP computer module of SCALE computer code. The radiation shielding of the cask was evaluated using the MCNP6 computer code. In addition, the evaluation of the radiation dose rate outside the transport cask required by the technical standard was classified into normal and accident conditions. Thus, the maximum radiation dose rates calculated at the surface of the cask and at a point 2 m from the surface of the cask under normal transportation conditions were respectively 0.330 mSv·h^-1 and 0.065 mSv·h^-1. The maximum radiation dose rate 1 m from the surface of the cask under accident conditions was calculated as 0.321 mSv·h^-1. Thus, it was confirmed that the spent fuel cask of the large capacity heavy water reactor had secured the radiation safety.

• Journal of the Korean Society of Manufacturing Process Engineers
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• v.18 no.3
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• pp.7-13
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• 2019

Recently, an automobile market used to natural gas has emerged as fast-growing as the several countries, who holds abundant natural fuel resources, has promoted to supply the national agency for an automobile car. LNG fuel vessel is more efficient in another way as the energy density is high, but it requires a high technology and investment to maintain extreme low temperature. CNG fuel vessel are relatively low-cost alternative to LNG, but poorly economical in terms of energy density as well as showing safety issues associated with compressed pressure. The development of adsorbed natural gas (ANG) has emerged as one of potential solutions. Therefore, it is desirable to reduce the weight of vessel by applying light-weighed a composite carbon fiber in order to response to the regulation of $CO_2$ emission. Herein, this study make the prototype ANG vessel not only based on the optimal design and analysis of material characteristic but also based on the shape design, and it suggest a new type for the composite carbon fiber vessel which verified functional test. Moreover, the detail shape design is analyzed by a finite element analysis, and its verifies the ANG vessel.

• Composites Research
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• v.21 no.1
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• pp.1-7
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• 2008

Composite vessels for high pressure gas storage are commonly used these days because of their competitive weight reduction ability maintaining strong mechanical properties. To supplement permeability of composite under high pressure, it is usually lined by metal, which is called a Type 3 vessel. However, it has many difficulties to design the Type 3 vessel because of its complex geometry, fabrication process variables, etc. In this study, therefore, GUI (graphic user interface) optimal design code for Type 3 vessels was developed based on semi-geodesic algorithm in which various factors of geometry and fabrication variables are considered and genetic algorithm for optimization. In addition, hydrogen vessels for 350/700 bar that can be applied to FCVs(fuel cell vehicles) were designed using this code for verification.