• Nuclear Engineering and Technology
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• 제43권6호
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• pp.489-498
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• 2011

UK National Nuclear Laboratory's (NNL's) version of the ENIGMA fuel performance code is described, including details of the development history, the system modelled, the key assumptions, the thermo-mechanical solution scheme, and the various incorporated models. The recent development of ENIGMA in the areas of whole core analysis and dry storage applications is then discussed. With respect to the former, the NEXUS code has been developed by NNL to automate whole core fuel performance modelling for an LWR core, using ENIGMA as the underlying fuel performance engine. NEXUS runs on NNL's GEMSTONE high performance computing cluster and utilises 3-D core power distribution data obtained from the output of Studsvik Scandpower's SIMULATE code. With respect to the latter, ENIGMA has been developed such that it can model the thermo-mechanical behaviour of a given LWR fuel rod during irradiation, pond cooling, drying, and dry storage - this involved: (a) incorporating an out-of-pile clad creep model for irradiated Zircaloy-4; (b) including the ability to simulate annealing out of the clad irradiation damage; (c) writing of additional post-irradiation output; (d) several other minor modifications to allow modelling of post-irradiation conditions.

• 한국항공우주학회지
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• 제42권6호
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• pp.445-452
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• 2014

본 논문은 제한된 계산 자원을 가진 환경에서 대규모 구조해석을 위해 고안된 보조기억장치를 활용하는 선형 직접해법에 대해 논의한다. 대용량 구조해석은 많은 기억공간과 계산량을 요구하기에 계산 자원이 부족할 경우 보조기억장치를 활용하는 해법을 개발할 필요가 있다. 본 연구는 한정된 주기억장치의 활용성을 극대화하고 상대적으로 느린 보조기억장치 저장량을 최소화하는 다중프론트 해법의 알고리즘을 소개한다. 구조해석 문제의 대칭성을 활용한 스택 공간 사용 기법과 역순 스택 자료 구조, 데이터 블록 크기에 따른 선택적 저장 기법과 데이터 복원 기법을 제시하였다. 본문에서 논의된 방법들을 적용한 다중프론트 해법이 여러 성능비교 문제에서 더 나은 계산 성능을 보임을 확인할 수 있다.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2005년도 학술발표회 논문집
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• pp.453-460
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• 2005

In this study, the seismic fragility analysis of a base isolated condensate storage tank installed in the nuclear power plant. The condensate storage tank is safety related structure in a nuclear power plant. The failure of this tank affect significantly to the core damage frequency of the nuclear power plants. The seismic analysis of the liquid storage tank was performed by the simple calculation method and the dynamic time storage analysis method. The convective and impulsive fluid mass is modeled as added masses proposed by several researchers. To evaluate the effectiveness of the isolation system, the comparison of HCLPF and core damage frequencies in non-isolated and isolated cases are carried out. It can be found from the results that the seismic isolation system increases the seismic capacity of a condensate storage tank and decreases the core damage frequency significantly.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.591-597
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• 2003

The demand of LNG in Korea has dramatically increased since it was first imported in 1986. Thus, more LNG storage tanks are required to meet the growing consumption of LNG. However the design, construction, and analysis of LNG storage facility need highly advanced technology compared to the general structures due to the fluid-structure interaction and the low temperature of LNG. Recently Korea Gas Corporation(KOGAS) constructed a pilot LNG storage tank, and it is in operation to develop and accumulate the core technology. As a part of those objects, the fundamental dynamic test for the pilot tank were performed. For this study, dynamic test were carried out and the dynamic characteristics of the pilot tank were verified and analyzed.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.635-641
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• 2016

Because of prohibitive data storage requirements in large-scale simulations, the memory problem is an obstacle for Monte Carlo (MC) codes in accomplishing pin-wise three-dimensional (3D) full-core calculations, particularly for whole-core depletion analyses. Various kinds of data are evaluated and quantificational total memory requirements are analyzed based on the Reactor Monte Carlo (RMC) code, showing that tally data, material data, and isotope densities in depletion are three major parts of memory storage. The domain decomposition method is investigated as a means of saving memory, by dividing spatial geometry into domains that are simulated separately by parallel processors. For the validity of particle tracking during transport simulations, particles need to be communicated between domains. In consideration of efficiency, an asynchronous particle communication algorithm is designed and implemented. Furthermore, we couple the domain decomposition method with MC burnup process, under a strategy of utilizing consistent domain partition in both transport and depletion modules. A numerical test of 3D full-core burnup calculations is carried out, indicating that the RMC code, with the domain decomposition method, is capable of pin-wise full-core burnup calculations with millions of depletion regions.

• 한국식품저장유통학회지
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• 제13권5호
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• pp.589-595
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• 2006

본 연구에서는 배추를 품종별, 부위별, 저장기간 동안의 vitamin U, amino acid 및 유리당 함량을 분석하고 변화경향을 조사하여 보았다. Vitamin U의 함량은 배추의 품종과 부위에 따라 차이를 나타내는 것으로 조사되었다. 동풍 배추(Winter Pride)의 겉잎(outward leaf)에서 12.70 mg/100 g, 55일 배추(55 Days)의 속잎(core leaf)에서 18.60 mg/100 g으로 vitamin U의 함량이 가장 높은 것으로 나타나 품종별 함량차이가 있음을 확인할 수 있었으며, 부위별 함량을 측정하여 본 결과 두 품종 모두 배추의 leaf부위가 midrib 부위에 비하여 1.7-9.0배 이상 높은 것으로 조사되었다. $4^{\circ}C$ 저장 동안의 vitamin U 함량은 두 품종 모두 다소 증가하는 것으로 나타났다. 저장 동안의 vitamin U의 전구체인 methionine 함량을 조사하여 본 결과 아주 낮거나 존재하지 않는 것으로 조사되었는데 이는 배추가 성숙하는 동안 methionine이 vitamin U 전구물질로 사용된 것으로 추정되어진다. 그러나, $4^{\circ}C$ 저장 동안의 vitamin U과 methionine의 함량에 대한 뚜렷한 상관관계는 보이지 않았으며 유리 amino acid와 유리당 함량과의 관계에 대한 더 많은 연구가 수행되어야 할 것으로 사료되어진다.

• Nuclear Engineering and Technology
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• 제52권2호
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• pp.248-257
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• 2020

This study presents an initial design for a novel system consisting in a coupled nuclear reactor and a phase change material-based thermal energy storage (TES) component, which acts as a buffer and regulator of heat transfer between the primary and secondary loops. The goal of this concept is to enhance the capacity factor of nuclear power plants (NPPs) in the case of high integration of renewable energy sources into the electric grid. Hence, this system could support in elevating the economics of NPPs in current competitive markets, especially with subsidized solar and wind energy sources, and relatively low oil and gas prices. Furthermore, utilizing a prismatic-core advanced high temperature reactor (PAHTR) cooled by a molten salt with a high melting point, have the potential in increasing the system efficiency due to its high operating temperature, and providing the baseline requirements for coupling other process heat applications. The present research studies the neutronics and thermal hydraulics (TH) of the PAHTR as well as TH calculations for the TES which consists of 300 blocks with a total heat storage capacity of 150 MWd. SERPENT Monte Carlo and MCNP5 codes carried out the neutronics analysis of the PAHTR which is sized to have a 5-year refueling cycle and rated power of 300 MW_th. The PAHTR has 10 metric tons of heavy metal with 19.75 wt% enriched UO₂ TRISO fuel, a hot clean excess reactivity and shutdown margin of $33.70 and -$115.68; respectively, negative temperature feedback coefficients, and an axial flux peaking factor of 1.68. Star-CCM + code predicted the correct convective heat transfer coefficient variations for both the reactor and the storage. TH analysis results show that the flow in the primary loop (in the reactor and TES) remains in the developing mixed convection regime while it reaches a fully developed flow in the secondary loop.

• 한국가스학회지
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• 제7권3호
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• pp.18-23
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• 2003

한국에서의 LNG에 대한 수요는 처음 수입된 1986년 이후로 크게 증가하고 있다. 따라서 LNG 소비에 맞추어 LNG 저장탱크의 확충이 요구된다. 그러나 LNG 저장 설비에 대한 설계, 건설 그리고 분석 분야에서는 유체-구조의 상호 작용과 LNG의 저온 특성 때문에 고정도의 선진 기술이 요구된다. 최근 한국가스공사에서는 Pilot LNG 저장탱크를 건설하였으며 실제 운전을 통한 핵심 기술을 개발하여 축척하고 있다. 한 부분의 연구로서 기초 동특성 시험을 실시하였다. 본 연구에서는 동특성 실험을 수행하였으며, Pilot LNG 저장탱크에 대한 동특성을 검증 및 분석하였다.

• 지구물리
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• 제5권2호
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• pp.75-86
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• 2002

평택 및 인천의 액화석유가스(LPG) 지하저장기지에 대해 VSP(Vertical Seismic Profiling)탐사를 터널에 응용한 TSP(Tunnel Seismic Prediction)탐사를 시공 중에 실시하였다. 평택 LPG 지하저장기지에서의 TSP탐사는 저장동굴이 위치한 남양호 하부에 존재하고 사전조사단계에서 파악된 단층의 방향과 규모를 확인하기 위하여 실시하였다. 단층의 위치 및 규모를 입체적으로 파악하기 위하여 진입터널, 수벽공터널 및 공사용터널에서 TSP탐사를 수행하였으며, 진입터널에서 천공된 4공의 조사 공과 비교되었다. TSP탐사 결과는 조사공 결과와 일치하였고, 파악된 단층대의 위치에 따라 기존에 설계된 저장동굴의 배치와 연장을 변경하였다. 해저에 건설된 인천 LPG 지하저장기지의 경우 시공 중에 많은 출수가 있어 효과적인 지수를 위해 지질구조에 대한 정확한 파악이 요구되었다. TSP탐사에 의한 파쇄대 분포의 파악으로 적절한 지보 및 그라우팅 대책이 이루어졌다.

• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2667-2677
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• 2020

A domain decomposition (DD) scheme for GPU-based Monte Carlo (MC) calculation which is essential for whole-core depletion is introduced within the framework of the modified history-based tracking algorithm. Since GPU-offloaded MC calculations suffer from limited memory capacity, employing DDMC is inevitable for the simulation of depleted cores which require large storage to save hundreds of newly generated isotopes. First, an automated domain decomposition algorithm named wheel clustering is devised such that each subdomain contains nearly the same number of fuel assemblies. Second, an innerouter iteration algorithm allowing overlapped computation and communication is introduced which enables boundary neutron transactions during the tracking of interior neutrons. Third, a bank update scheme which is to include the boundary sources in a way to be adequate to the peculiar data structures of the GPU-based neutron tracking algorithm is presented. The verification and demonstration of the DDMC method are done for 3D full-core problems: APR1400 fresh core and a mock-up depleted core. It is confirmed that the DDMC method performs comparably with the standard MC method, and that the domain decomposition scheme is essential to carry out full 3D MC depletion calculations with limited GPU memory capacities.