• 한국화재소방학회논문지
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• 제24권4호
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• pp.116-122
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• 2010

원자력발전소는 심층화재방어 개념에 따라 화재 발생시 발전소 외부로 방사능의 누출을 억제하고, 발전소의 안전정지 기능이 유지될 수 있도록 설계, 건설, 운영되어야 한다. 해외의 원전건설 국가는 이러한 원자력발전소의 안전정지 기능의 목적을 달성하기 위하여 원자력발전소에 대한 통합된 화재방호 규제요건을 가지고 있으나, 우리나라의 경우, 원자력발전소의 화재방호계통을 적용하기 위한 강제 요건으로서 소방관계법과 원자력법을 동시에 적용하는 비합리적인 규제지침을 가지고 있다. 화재방호설비에 관하여 원자력발전소 운영에 오랜 경험을 가진 미국, 캐나다 및 일본의 기술적으로 단일화된 원자력발전소의 화재방호 규제체계를 제시하였고, 우리나라도 화재방호설비는 원자력법에 의한 화재하중에 따른 화재위험도분석 결과를 설계에 반영하여 소방관계법에서는 예외조항으로 인정받을 수 있어야 함을 제안하였다.

• Nuclear Engineering and Technology
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• 제34권3호
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• pp.259-267
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• 2002

NFPA-803 has been referred as the Fire Protection Standard at the Nuclear Power Plants of Pressurized Water Reactor. This Standard has been used as the fire protection regulation, containing prescriptive requirements with deterministic methodology. Recently, with cumulative efforts by the U.S. Nuclear Regulatory Commission and Utilities in America to establish a new Standard, including a quantitative evaluation methodology, NFPA-805, the Performance-Based Standard for FIRE Protection for Light Water Reactor Electric Generating Plants was issued and approved by the American National Standards Institute as an American National Standard with an effective date of February 9, 2001. This paper presents an analysis result from the computer modeling for the fire simulation In addition, it proposes the idea that this kind of analytic method can be available for the facilities design of fire prevention and protection fields, as well as an evaluation for the fire suppression system with a quantitative analysis for the thermal phenomena in fire compartments in Nuclear Power Plants.

• Journal of Radiation Protection and Research
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• 제28권2호
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• pp.137-143
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• 2003

Annual radiation dose limit to radiation worker was substantially lowered in Korea by the adoption of 1990 recommendations of the International Commission on Radiation Protection (ICRP 60) in its legislation. On the other hand, radiation management environment in nuclear power plants is getting more worse because of the accumulation of radiation sources inside the system and the frequent need for maintenance according as the operation years of nuclear power plants increase. Therefore, Korea Hydro & Nuclear power Co., Ltd. (KHNP) has established a long-term 10 years plan from 2001 to 2010 for the reduction of radiation dose to workers. The plan is aimed for the reduction of annual dose per unit averaged over 5 years from 0.9 man-Sv in 2001 to 0.75 man-Sv in 2010 by radiation source reduction, equipment/tool improvement or new equipment development for easy maintenance, and the improvement of administration and system.

• Nuclear Engineering and Technology
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• 제48권1호
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• pp.211-217
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• 2016

Most nuclear power plants now utilize solid grounded low voltage systems. For safety and reliability reasons, the low voltage (LV) high resistance grounding (HRG) system is also increasingly used in the pulp and paper, petroleum and chemical, and semiconductor industries. Fault detection is easiest and fastest with a solidly grounded system. However, a solidly grounded system has many limitations such as severe fault damage, poor reliability on essential circuits, and electrical noise caused by the high magnitude of ground fault currents. This paper will briefly address the strengths and weaknesses of LV grounding systems. An example of a low voltage HRG system in the LV system of a nuclear power plant will be presented. The HRG system is highly recommended for LV systems of nuclear power plants if sufficient considerations are provided to prevent nuisance tripping of ground fault relays and to avoid the deterioration of system reliability.

• 한국화재소방학회논문지
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• 제26권6호
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• pp.38-44
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• 2012

원자력발전소 화재방호의 목표는 화재 시 원자로의 안전정지 상태를 유지하여 환경으로의 방사성물질 누출을 최소화하며, 종사자 인명안전 및 재산을 보호하는데 있다. 소방시설은 발생된 화재를 조기 감지 및 진압하여 화재로 인한 피해를 완화시킬 수 있는 심층방어개념에 입각한 중요한 방어수단의 하나이다. 그러나 소방방재청에서 제시하고 있는 소방시설 설치기준이 원자력발전소에 특화되어 있지 않아 인허가 시 별도의 심의 절차가 요구되고 있다. 또한, 성능위주설계와 같은 규정은 작업자의 인구밀도가 비교적 낮은 원자력발전소에 적용하는데 어려움이 있다. 이 논문에서는 원전 화재방호와 관련된 법령의 상세 검토를 통하여 도출된 근본적인 문제점과 KEPIC FPN의 국내 원전 적용성에 대한 평가를 통하여 소방시설에 대한 기술기준에 대한 개선방향을 제시하였다.

• 디지털산업정보학회논문지
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• 제18권2호
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• pp.39-48
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• 2022

The application of digital technology to instrumentation and control systems in nuclear power plants has overcome many shortcomings of analog technology, but the threat of cybersecurity has increased. Along with other systems, the reactor protection system also uses digital-based equipment, so responding to cybersecurity threats is essential. We generally determine cybersecurity threats according to the role and function of the system. However, since the instrumentation and control system has various systems linked to each other, it is essential to analyze cybersecurity threats together between the connected systems. In this paper, we analyze the cybersecurity threat of the reactor protection system with the associated facilities. To this end, we quantitatively identified the risk of the reactor protection system by considering safety functions, a communication type, the use of analog or digital-based equipment of the associated systems, and the software vulnerability of the configuration module of the reactor protection system.

• 한국화재소방학회:학술대회논문집
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• 한국화재소방학회 2003년도 춘계학술논문발표회논문집
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• pp.259-264
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• 2003

The fire protection system of Nuclear Power Plants(NPPs) is an integrated system that is applied multi-field technology. So, it needs synthetic design and analysis, that is, the plan of fire protection, fire compartment, fire detection, fire suppression, and success of safety shut down, etc. In case of a fire in NPPs, secure the safety of reactor and minimize the radioactivity contamination. For this purpose, perform the fire risk analysis and make up the deducted problem through the improvement of design or the change of operation process.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 심포지엄 논문집 정보 및 제어부문
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• pp.84-86
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• 2005

The digital systems such as PLC or DCS have been applied to non-safety systems of nuclear power plants because of many difficulties in using analog systems. Nowadays, digital systems have been applied to safety systems of the plants such as reactor protection system. One of the main advantages of digital systems is applicability of automatic testing methods to the systems. The protection system requires high-reliability and high-availability because it shall minimize the propagation of abnormal or accident conditions of nuclear power plants. The calculation of reliability and availability of systems depends on the maintenance period of the system. In general, the maintenance period of the protection system is one-month in case of the manual test. However, the cycle of test can be shortened in several hours by using automatic periodic testing. The reliability and availability of the system is better when test period is shortened because the reliability and availability is inverse proportion to the test period. In this research, we developed the automatic periodic testing method for KNICS Reactor Protection System, which can test the system automatically without an operator or a tester. The automatic testing contained all functions of reaction protection systems from analog-to-digital conversion function of the bistable Processor to the coincident trip function of the coincident processor. By applying the automatic periodic testing to reaction system, the maintenance cost can be cut down and the reliability can be increased.

• 한국화재소방학회논문지
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• 제25권5호
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• pp.54-61
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• 2011

UAE(United Arab Emirates) 원전(원자력발전소)의 수출을 목적으로 UAE, 미국, 일본, 한국의 원전 화재방호규정을 상호 비교 검토하였다. UAE를 포함하여 미국, 일본의 원전 화재방호규정은 화재하중에 따른 화재위험도 분석결과에 따라 소화설비를 설치하도록 규정하고 있다. 반면, 우리나라는 소방관계법에서 원전을 발전시설로 구분하고 있으나, 원자력법에서는 원자로 및 관계시설로 분류하고 있고, 각 법률간 화재방호 설계기준도 상이하다. 앞으로 우리나라가 원전 수출국의 지위를 계속적인 유지하기 위해서는 화재 위험도분석의 결과가 설계에 반영될 수 있어야 한다. 결론으로, 국내 소방관계법이 원전의 특수성을 반영하기 위해서는 소방시설공사업법 시행령 제2조 2항의 성능위주설계를 해야 할 특정소방대상물에 원전이 추가되어야 함을 제안하였다.

• Corrosion Science and Technology
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• 제14권1호
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• pp.12-18
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• 2015

Since the operation period of nuclear power plants has increased, the degradation of buried pipes gradually increases and recently it seems to be one of the emerging issues. Maintenance on buried pipes needs high quality of management system because outer surface of buried pipe contacts the various soils but inner surface reacts with various electrolytes of fluid. In the USA, USNRC and EPRI have tried to manage the degradation of buried pipes. However, there is little knowledge about the inspection procedure, test and manage program in the domestic nuclear power plants. This paper focuses on the development and build-up of real-time monitoring and control system of buried pipes. Pipes to be tested are tape-coated carbon steel pipe for primary component cooling water system, asphalt-coated cast iron pipe for fire protection system, and pre-stressed concrete cylinder pipe for sea water cooling system. A control system for cathodic protection was installed on each test pipe which has been monitored and controlled. For the calculation of protection range and optimization, computer simulation was performed using COMSOL Multiphysics (Altsoft co.).