• Nuclear Engineering and Technology
• /
• 제45권5호
• /
• pp.597-604
• /
• 2013

Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europe and Canada for the controlled depressurization of the containment atmosphere under severe accident conditions. This is to keep the containment integrity against overpressure during the course of a severe accident, in which the radioactive gas-steam mixture from the containment is discharged into a system designed to remove the radionuclides. In Korea, a CFVS was first introduced in the Wolsong unit-1 nuclear power plant as a mitigation measure to deal with the threat of over pressurization, following post-Fukushima action items. In this paper, the overall features of a CFVS installation such as risk assessments, an evaluation of the performance requirements, and a determination of the optimal operating strategies are analyzed for the Wolsong unit 1 nuclear power plant using a severe accident analysis computer code, ISAAC.

• Nuclear Engineering and Technology
• /
• 제55권6호
• /
• pp.2053-2068
• /
• 2023

Following a loss of coolant accident (LOCA), prestressing concrete containment vessels (PCCVs) may experience high thermal load as well as internal pressure. The high temperature stress would increase the risk of premature damage to the containment, which reduces the safety margin during the increasing internal pressure. However, current investigations cannot clearly address the issues of thermal-pressure coupling effect on damage propagation and thus safety of the containment. Thus, this paper offers three simple and powerful damage parameters to differentiate the severity of damage of the containment. Moreover, despite of the temperature action severely threatening the pressure performance of the containment, the research regarding the improvement of the resistant performance of the containment is quite scarce. Therefore, in this paper, a comprehensive comparison of damage propagation and mechanism between conventional and fiber-reinforced concrete (FRC) containments is performed. The effects of fiber characteristics parameters on damage propagation of structures following the LOCA are also specifically revealed. It is found that the proposed damage indices can properly indicate state of damage in the containment body and the addition of fiber can be used to obviously mitigate the damage propagation in PCCV considering the thermal-pressure coupling.

• Nuclear Engineering and Technology
• /
• 제48권4호
• /
• pp.975-981
• /
• 2016

The containment response during the first 24 hours of a low-pressure severe accident scenario in a nuclear power plant with a two-loop Westinghouse-type pressurized water reactor was simulated with the CONTAIN 2.0 computer code. The accident considered in this study is a large-break loss-of-coolant accident, which is not successfully mitigated by the action of safety systems. The analysis includes pressure and temperature responses, as well as investigation into the influence of spray on the retention of fission products and the prevention of hydrogen combustion in the containment.

• Nuclear Engineering and Technology
• /
• 제29권5호
• /
• pp.368-374
• /
• 1997

This paper presents a new approach to the evaluation of an accident management strategy when an operator action is involved. This approach classifies the failure in implementing a given strategy into 4 possible mechanisms, and provides their corresponding quantification methods : 1) the failure to formulate correct intention by operators, 2) the failure to take an adequate action following a correct diagnosis, 3) the failure of a system operation following an adequate action, and 4) the failure due to a delayed action. The proposed method was applied to assess a cavity flooding strategy that uses containment spray system (CSS), and the result shows that the method is more appropriate in evaluating accident management strategies when human action is involved.

• 한국안전학회지
• /
• 제33권6호
• /
• pp.136-143
• /
• 2018

In this study, we conducted a pilot study on the multiple spurious operations (MSO) analysis in the fire probabilistic safety assessment (PSA) of domestic nuclear power plant (NPP) to identify the degree of influence of the operator actions used in the MSO mitigation strategies. The MSO scenario of the domestic reference NPP selected for this study is refueling water tank (RWT) drain down event. It could be caused by spurious operations of the containment spray system (CSS) of the reference NPP. The RWT drain down event can be stopped by the main control room (MCR) operator actions for stopping the operation of CSS pump or closing the CSS motor operated valve if the containment spray actuation signal (CSAS) is spuriously actuated. Outside the MCR, it can be stopped by operator actions for closing the CSS manual valves or motor operated valve or stopping the operation of CSS pump. The quantification result of a fire PSA model that takes into account all recovery actions for the RWT drain down event lead to risk reduction by about 95%, compared with quantification result of fire PSA model without considering them. Among the various operator actions, the recovery action for the spurious CSAS operations and the operator action for the manual valve are identified as the most important operator actions. This study quantitatively showed the extent to which the operator actions used as MSO countermeasures have affected the fire PSA quantification results. In addition, we can see the rank of importance among the operator recovery actions in quantitative terms.

• International Journal of Ocean System Engineering
• /
• 제1권4호
• /
• pp.230-235
• /
• 2011

Reinforced polyurethane foam (RPUF) is one of the important materials of Mark III type insulation systems used in liquefied natural gas (LNG) cargo containment systems. However, RPUF is the most difficult material to use with regard to its safety assessment, because there is little public and reliable data on its mechanical properties, and even some public data show relatively large differences. In this study, to investigate the structural response of the system under compressive loads such as sloshing action, time-dependent characteristics of RPUF were examined. A series of compressive load tests of the insulation system including RPUF under various temperature conditions was carried out using specimens with rectangular section. As a result, the relationship between deformation of RPUF and time is linear and dependent on the loading rate, so the concept of strain rate could be applied to the analysis of the insulation system. Also, we found that the spring constant tends to converge to a value as the loading rate increases and that the convergence level is dependent on temperature.

• 한국정보과학회논문지:컴퓨팅의 실제 및 레터
• /
• 제6권1호
• /
• pp.58-67
• /
• 2000

엔터프라이즈 네트웍의 크기가 커지고 그 관리 범위가 넓어짐에 따라 분산 망 관리 시스템의 수용을 요구하게 되었고 또한 표준 프레임웍들간의 상호 연결 및 작용이 필요하게 되었다. 이 논문에서는 네트웍 관리 프레임웍인 SNMP도메인과 분산 객체 기술의 하나인 CORBA도메인간의 통합 관리를 위한 구현 방안을 제시한다. 표준에서 사용하는 직접 변환은 객체 지향적인 특성을 표현하고 있지 않으며, action을 위한 속성의 정의가 다른 속성과 구별되지 않는 등의 한계를 지니고 있다. 이러한 한계점은 추상적 변환 방법을 통해 새로운 클래스의 정의, 명확한 메쏘드 정의라는 방법으로 충분히 극복될 수 있다. 직접 변환의 편리함과 추상적 변환의 효율적인 관리 정보의 구축이라는 장점을 이용한 직접 변환과 추상적 변환의 혼용을 통한 정보 모델 변환 방법을 이용한 게이트웨이의 개발 방법을 제시한다. 이러한 통합 관리 시스템 구축은 CORBA/SNMP 간의 효율적인 통합 관리를 제공한다.

• Structural Engineering and Mechanics
• /
• 제10권6호
• /
• pp.533-543
• /
• 2000

To prevent major cracking and failure during earthquakes, it is important to design reinforced concrete liquid storage structures, such as water and fuel storage tanks, properly for the hydrodynamic pressure loads caused by seismic excitations. There is a discussion in recent Codes that most of the base shear applied to liquid containment structures is resisted by inplane membrane shear rather than by transverse flexural shear. The purpose of this paper is to underline the importance of the membrane force system in carrying the base shear produced by hydrodynamic pressures in both rectangular and cylindrical tank structures. Only rigid tanks constrained at the base are considered. Analysis is performed for both tall and broad tanks to compare their behavior under seismic excitation. Efforts are made to quantify the percentage of base shear carried by membrane action and the consequent procedures that must be followed for safe design of liquid containing storage structures.

• 한국전자통신학회논문지
• /
• 제10권11호
• /
• pp.1205-1216
• /
• 2015

인간의 화석연료 사용, 도시화, 경작 등으로 인해 온실가스의 농도는 계속 증가하여 기후변화가 나타나고 있는 추세이다. 이로 인해 20세기는 재난의 발생이 돌발적이고 대형화되고 있으며, 피해 규모 역시 점차 증가하는 실정이다. 따라서 과거와 다른 양상의 신종 재난에 대해 국토를 보존하고 국민의 생명과 재산을 보호하기 위해서는 재난탐지위성(탑재체) 개발이 시급히 요구된다. 본 논문에서는 불규칙한 미래재난에 대해 광역적이고, 한국지형에 최적화된 재난 관측과 재난발생 시 신속한 선제 대응을 위한 기술개발 연구를 수행하고자 한다. 이를 위해 재난 탐지 특화 탑재체 설계를 위해 10개의 재난 유형별 위성영상 활용 사례를 바탕으로 테크트리를 작성하고 국외의 유사 활용위성센서인 Landsat-8, Worldview-3, ALOS-2를 참고하여 재난탐지에 최적화된 위성 센서 기술요구조건을 분석하였다.

• 한국압력기기공학회 논문집
• /
• 제17권2호
• /
• pp.90-100
• /
• 2021

Molten corium-concrete interaction (MCCI) is one of the most important phenomena that can lead to the potential hazard of late containment failure due to basemat penetration during a severe accident. In this study, MCCI analytical models of the CORQUENCH code were prepared through verification calculations of several experiments, which had been performed using concrete types similar to those of the calandria vault floor in CANDU-6 plants. The behaviors of thermal-hydraulic variables related to MCCI phenomena were analyzed under the conditions of dry floor and water flooding during the severe accident stemming from a hypothetic station blackout. Uncertainty analyses on the ablation depth were also carried out. It was estimated that the concrete ablation was not interrupted due to the continuous MCCI process under the dry condition but was terminated within 24 hours under the water flooding condition. It was confirmed that the water flooding as a mitigating action was effective to achieve the quenching and thermal stabilization of the melt discharged from the calandria vessel, showing that the present models are capable of reasonably simulating MCCI phenomena in CANDU-6 plants. This study is expected to provide the technical bases to the accident management strategy during the late-phase severe accidents.