• 한국안전학회지
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• 제33권3호
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• pp.92-98
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• 2018

The flow of cooling water in a passive containment cooling system (PCCS), used to remove heat released in design basis accidents from a concrete containment of light water nuclear power plant, was conducted in order to investigate the thermo-fluid equilibrium among many parallel tubes of PCCS. Numerical simulations of the subcooled boiling flow within a coolant loop of a PCCS, which will be installed in innovative pressurized-water reactor (PWR), were conducted using the commercially available computational fluid dynamics (CFD) software ANSYS-CFX. Shear stress transport (SST) and the RPI model were used for turbulence closure and subcooled flow boiling, respectively. As the first step, the simplified geometry of PCCS with 36 tubes was modeled in order to reduce computational resource. Even and uneven thermal loading conditions were applied at the outer walls of parallel tubes for the simulation of the coolant flow in the PCCS at the initial phase of accident. It was observed that the natural circulation maintained in single-phase for all even and uneven thermal loading cases. For uneven thermal loading cases, coolant velocity in each tube were increased according to the applied heat flux. However, the flows were mixed well in the header and natural circulation of the whole cooling loop was not affected by uneven thermal loading significantly.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.431-432
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• 2004

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2011년도 제36회 춘계학술대회논문집
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• pp.414-417
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• 2011

본 논문에서 Compressor 및 turbine 에서의 Blade failure등의 내부파손이 이를 둘러싸고 있는 케이스 내부에 머무르게 하는 엔진설계의 방법에 대한 이론 및 Simulation 등을 기술 하였다. 가장 무거운 부품 중에 하나인 케이스의 두께 최적화는, 항공기의 안정성뿐만 아니라 항공 효율을 높이기 위한 경량화의 목적을 위해서도 매우 중요한 설계목표 이다. 이러한 목적을 위하여 이론적 접근방법으로 에너지 밸런스 방법을 사용하였으며, 파손된 블레이드의 거동특성 및 영향성 평가를 위한 유한요소해석을 위하여 LS-DYNA가 사용 되어졌다.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1513-1525
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• 2024

An improved mitigation system for thermally-induced steam generator tube rupture accidents was introduced to prevent direct environmental release of fission products bypassing the containment in the OPR1000. This involves injecting bypassed steam into the containment, cooling, and decontaminating it using a water coolant tank. To evaluate its performance, a severe accident analysis was performed using the MELCOR 2.2 code for OPR1000. Simulation results show that the proposed system sufficiently prevented the release of radioactive nuclides (RNs) into the environment via containment injection. The pool scrubbing system effectively decontaminated the injected RN and consequently reduced the aerosol mass in the containment atmosphere. However, the decay heat of the collected RNs causes re-vaporization. To restrict the re-vaporization, an external water source was considered, where the decontamination performance was significantly improved, and the RNs were effectively isolated. However, due to the continuous evaporation of the feed water caused by decay heat, a substantial amount of steam is released into the containment. Despite the slight pressurization inside the containment by the injected and evaporated steam, the steam decreased the hydrogen mole fraction, thereby reducing the possibility of ignition.

• 한국가스학회지
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• 제11권4호
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• pp.85-90
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• 2007

본 논문에서는 유한요소법을 사용하여 댐핑안전 구조물을 설치한 완전밀폐식 LNG 저장탱크 시스템의 강도안전성에 대해 해석하였다. 내부탱크의 FEM 해석을 위해, 탱크에 저장된 LNG에 의한 유체정압, 초저온 온도하중, BOG 압력, LNG 자중량, 내부탱크의 코너 측벽면에 가해진 침하하중 등과 같은 모든 복합하중을 내부탱크 구조물에 적용하였다. FEM 계산결과에 의하면 기존의 내부탱크는 주어진 모든 하중 조건에 대하여 안전하지만, 압축 스프링과 같은 댐핑안전 구조물은 탱크시스템의 안전성을 확보하는데 대단히 유용한 구조물일 것이라는 사실이다. 따라서 스프링의 강점도를 높이고 최적의 설치위치를 찾으면 스프링 구조물에 의해 탱크시스템의 댐핑강도 안전성을 증가시킬 수 있는 중요한 설계요소가 될 것이다.

• Nuclear Engineering and Technology
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• 제46권2호
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• pp.207-216
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• 2014

This paper revisits the Fukushima accident to draw lessons in the aspect of nuclear safety considering the fact that the Fukushima accident resulted in core damage for three nuclear power plants simultaneously and that there is a high possibility of a failure of the integrity of reactor vessel and primary containment vessel. A brief review on the accident progression at Fukushima nuclear power plants is discussed to highlight the nature and characteristic of the event. As the severe accident management measures at the Fukushima Daiich nuclear power plants seem to be not fully effective, limitations of current severe accident management strategy are discussed to identify the areas for the potential improvements including core cooling strategy, containment venting, hydrogen control, depressurization of primary system, and proper indication of event progression. The gap between the Fukushima accident event progression and current understanding of severe accident phenomenology including the core damage, reactor vessel failure, containment failure, and hydrogen explosion are discussed. Adequacy of current safety goals are also discussed in view of the socio-economic impact of the Fukushima accident. As a conclusion, it is suggested that an investigation on a coherent integrated safety principle for the severe accident and development of innovative mitigation features is necessary for robust and resilient nuclear power system.

• Nuclear Engineering and Technology
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• 제47권7호
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• pp.827-837
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• 2015

Following a severe accident in a nuclear power plant, iodine is a major contributor to the potential health risks for the public. Because the amount of iodine released largely depends on its volatility, iodine's behavior in containment has been extensively studied in international programs such as International Source Term Programme-Experimental Program on Iodine Chemistry under Radiation (EPICUR), Organization for Economic Co-operation and Development (OECD)-Behaviour of Iodine Project, and OECD-Source Term Evaluation and Mitigation. Korea Institute of Nuclear Safety (KINS) has joined these programs and is developing a simplified, stand-alone iodine chemistry model, RAIM (Radio-Active Iodine chemistry Model), based on the IMOD methodology and other previous studies. This model deals with chemical reactions associated with the formation and destruction of iodine species and surface reactions in the containment atmosphere and the sump in a simple manner. RAIM was applied to a simulation of four EPICUR tests and one Radioiodine Test Facility test, which were carried out in aqueous or gaseous phases. After analysis, the results show a trend of underestimation of organic and molecular iodine for the gas-phase experiments, the opposite of that for the aqueous-phase ones, whereas the total amount of volatile iodine species agrees well between the experiment and the analysis result.

• 에너지공학
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• 제21권4호
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• pp.339-345
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• 2012

최근 안정성 및 경제성 측면에서 완전방호식 LNG 저장탱크(full-containment LNG storage tank)의 대안으로 검토되고 있는 멤브레인 LNG 저장탱크(membrane LNG storage tank)에 대해서 정량적 위험성 평가 방법(QRA; Quantitative Risk Analysis)과 유한요소해석법(FEM; Finite Element Method)을 통하여 안전성 평가를 수행하였다. 본 논문에서는 유한요소해석법(FEM)을 통한 구조안전성 평가에서 140,000 $m^3$ 저장용량을 갖는 LNG 저장탱크의 두 가지 모델은 저장탱크 시스템에 대한 강도 안전성과 누출 안전성 측면에서 해석한 결과에 의하면 모두 안전한 것으로 평가되었다. 또한, 고장수목분석(FTA; Fault Tree Analysis)을 통하여 멤브레인 LNG 저장탱크에 안전성을 강화하기 위해 설계 초기모델에 안전장치로서 멤브레인 바닥부의 충격흡수장치(impact absorber structure), 1차 멤브레인 저장 파손 시 콘크리트 외부탱크(outer tank) 코너부(corner part)의 열충격(thermal stress)을 감소시킬 수 있는 열보호장지(secondary barrier) 및 펌프 낙하 시 안전장치로서 펌프캐쳐(pump catcher)를 보완하고 평가하였다. 결론적으로 개선된 멤브레인 LNG 저장탱크는 안전성 측면에서 완전방호식 LNG 저장탱크와 대등하다는 결론을 도출할 수 있었다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.647-652
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• 1998

The YGN Units 3&4 plant conditions during shutdown operation were reviewed to identified the possible even scenarios following the loss of shutdown cooling. The Thermal hydraulic analyses were performed for the five cases of RCS configurations under the worst event scenario, unavailable secondary cooling and no RCS inventory makeup, using the RELAP5/MOD3.2 code to investigate the plant behavior, From the analyses results, times to boil, times to core uncovery and times to core heat up were estimated to determined the containment closure time to prevent the uncontrolled released of fission products to atmosphere, These data provide useful information to the abnormal procedure to cope with event.

• Nuclear Engineering and Technology
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• 제52권2호
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• pp.397-416
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• 2020

Investigations of the commercial aircraft impact effect on nuclear island infrastructures have been drawing extensive attention, and this paper aims to perform the safety assessment of Generation III nuclear power plant (NPP) buildings subjected to typical commercial aircrafts crash. At present Part II, based on the verified finite element (FE) models of aircrafts Airbus A320 and A380, as well as the NPP containment and auxiliary buildings in Part I of this paper, the whole collision process is reproduced numerically by adopting the coupled missile-target interaction approach with the finite element code LS-DYNA. The impact induced damage of NPP plant under four impact locations of containment (cylinder, air intake, conical roof and PCS water tank) and two impact locations of auxiliary buildings (exterior wall and roof of spent fuel pool room) are evaluated. Furthermore, by considering the inner structures in the containment and raft foundation of NPP, the structural vibration analyses are conducted under two impact locations (middle height of cylinder, main control room in the auxiliary buildings). It indicates that, within the discussed scenarios, NPP structures can withstand the impact of both two aircrafts, while the functionality of internal equipment on higher floors will be affected to some extent under impact induced vibrations, and A380 aircraft will cause more serious structural damage and vibrations than A320 aircraft. The present work can provide helpful references to assess the safety of the structures and inner equipment of NPP plant under commercial aircraft impact.