The tsunami hazard analysis is performed for testing the application of probabilistic tsunami hazard analysis to nuclear power plant sites in the Korean Peninsula. Tsunami hazard analysis is based on the seismic hazard analysis. Probabilistic method is adopted for considering the uncertainties caused by insufficient information of tsunamigenic fault sources. Logic tree approach is used. Uljin nuclear power plant (NPP) site is selected for this study. The tsunamigenic fault sources in the western part of Japan (East Sea) are used for this study because those are well known fault sources in the East Sea and had several records of tsunami hazards. We have performed numerical simulations of tsunami propagation for those fault sources in the previous study. Therefore we use the wave parameters obtained from the previous study. We follow the method of probabilistic tsunami hazard analysis (PTHA) suggested by the atomic energy society of Japan (AESJ). Annual exceedance probabilities for wave height level are calculated for the site by using the information about the recurrence interval, the magnitude range, the wave parameters, the truncation of lognormal distribution of wave height, and the deviation based on the difference between simulation and record. Effects of each parameters on tsunami hazard are tested by the sensitivity analysis, which shows that the recurrence interval and the deviation dominantly affects the annual exceedance probability and the wave heigh level, respectively.

Many countries have introduced new imported food safety measures, following the accident at Fukushima Daiichi Nuclear Power Station. This study was conducted to evaluate the measures contents and effects on food trades values. Eight percent of members were notified the introduced measures to the World Trade Organization. The measures’ contents were banning imports, enhancing inspection and adding certification requirement. The covered regions were some prefectures, entire Japan or all affected countries. European Union introduced a measure that subjecting foods originating from 12 prefectures to import at designated ports with required certification. The measures were amended 8 times until March 2014 to apply listed foods from 15 prefectures. The trade value of fishery products and miscellaneous foods were affected. Australia introduced a measure that required additional inspection of dairy, fishery and plants products from 13 prefectures with subsequent amendments. The trade value had no effect in tested foods. Chinese Taipei introduced a temporary import ban for all foods from 6 prefectures. Trade values for fruits were affected. The United States issued an import alert for detention without examination for listed prefectures and goods without introducing new measures. Although no specific products were affected, trade values for all foods were affected.

This study presents a structural safety analysis method for a plant annunciator panel under the seismic effect. Seismic qualification analysis for the nuclear plant annunciator panel is carried out to confirm the structural integrity and the results are represented by required response spectra. For the numerical analysis, finite element method is adopted. Mode combinations are also used to obtain the reliability of the spectrum analysis. The analysis results shows that the nuclear plant annunciator panel is designed as a dynamically rigid assembly, without any resonance frequency blow 33Hz. The calculated stress of the nuclear plant annunciator panel is much less than yield stress of used steel.

In this study, dynamic characteristics and seismic capacity of the nuclear power plant piping system are evaluated by model test results using multi-platform shake table. The model is 21.2 m long and consists of straight pipes, elbows, and reducers. The stainless steel pipe diameters are 60.3 mm (2 in.) and 88.9 mm (3 in.) and the system was assembled in accordance with ASME code criteria. The dynamic characteristics such as natural frequency, damping and acceleration responses of the piping system were estimated using the measured acceleration, displacement and strain data. The natural frequencies of the specimen were not changed significantly before and after the testing and the failure and leakage of the piping system was not observed until the final excitation. The damping ratio was estimated in the range of 3.13 ~ 4.98 % and it is found that the allowable stress(345 MPa) according to ASME criteria is 2.5 times larger than the measured maximum stress(138 MPa) of the piping system even under the maximum excitation level of this test.

Involved in a research for the application of seismic isolation to the nuclear industry, this study evaluates firstly the responses of seismic isolation system considering general ranges of structural period and damping ratio by using preliminary design formula. Secondly, coupling effects of input motions were evaluated to find out appropriate conditions of excitations and effect of the iteration for calculating yield displacement of lead core was also assessed in terms of response of a seismically isolated structure. Finally, the results of preliminary design calculation were compared with those of dynamic analysis and the propriety of the formula was evaluated and appropriate ranges of reduction factor were also suggested from the results.

An Emergency Diesel Generator (EDG) installed in a nuclear power plant is the primary power source, supplying AC power to Class 1E power systems when the main turbine generator and offsite power source are not available. Thus, reliability of the EGD is essential for plant safety and availability. In this paper, the EDG is selected for a Long Term Asset Management (LTAM) strategy and the results are summarized briefly. The LTAM strategy is intended to provide an effective long-term planning tool for minimizing unplanned capability loss and then optimizing maintenance programs and capital investments consistent with plant safety and an identified plant operating strategy. Such an operating strategy might include license renewal or retaining the option for license renewal.

원자력발전소에 설치되는 안전관련 캐비닛형 전기기기는 설치 전에 내진검증이 요구된다. 전기기기의 동특성분석은 내진 검증에 포함된 중요한 과정이며, 기기의 정확한 해석모델을 작성하기 위해서도 필수적으로 요구되는 업무이다. 이 연구에서는 입력진동수준에 따른 기기의 동특성 변화를 분석하기 위하여 원전 지진감시시스템 캐비닛을 대상으로 진동대시험을 수행하고, 입력진동운동의 수준별로 계측된 진동응답신호를 진동수영역분해법으로 분석하였다. 분석결과, 대상기기는 입력진동수준의 크기에 따라 동특성이 비선형적으로 변화하고, 국내 원전의 안전정지지진 수준 이하의 진동에서도 동특성이 비선형적 거동을 보이고 있음을 확인하였다. 이러한 입력진동 수준에 따라 전기기기의 동특성이 비선형적으로 변하는 원인은 대상기기의 특성과 입력진동수준을 고려할 때 일반적인 재료 비선형보다는 각 부품들의 마찰력과 기하학적인 비선형성에 기인하는 것으로 판단된다. 따라서 전기 캐비닛의 입력진동수준에 따른 동특성의 비선형적 변화는 향후 안전관련 기기의 내진검증 업무에서 중요하게 검토되어야 할 것으로 판단된다.

월성원자력발전소 주변해역에서 출현한 동물플랑크톤은 종 수준까지 동정이 가능한 32종을 포함하여, 총 63종과 85~28,087개체 m-3 범위였다. 연구해역에 분포하는 동물플랑크톤 군집의 구조를 분석한 결과, 전반적으로 배수구를 중심으로 북쪽과 동쪽에 위치한 정점군(그룹 A)과 취수구 아래쪽 정점군(그룹 B)의 두 개의 그룹으로 구분되었다. 동물플랑크톤 군집의 분리는 10월에 출현 종수가, 그 밖의 시기인 1월, 5월 및 8월에는 개체수가 영향

본 연구는 월성 원자력발전소 주변해역에 서식하는 대형저서동물의 출현 종수, 생물량 및 군집구조를 파악하기 위하여 2007년 10월부터 2008년 7월까지 계절별로 현장조사를 실시하였다. 총 163종의 대형저서동물이 출현하였고, 단위면적당 (m2) 개체수와 생체량은 각각 1,005개체와 21.81 gWWt이었다. 출현 개체수의 자료를 기초로 LeBris index (1988)를 이용하여 상위 10위까지의 우점종을 선정하였다. 개체수에 근거한 상위 1

본 연구는 원자력발전소에 설치되는 캐비닛형 전기기기의 동적 진동시험 자료를 이용하여 캐비닛의 지진응답을 예측할 수 있는 기법을 제안하였다. 제안된 기법은 1) 절점질량 이상화 모델에 기반한 등가 지진하중 산정, 2) 진동시험자료에 기반한 캐비닛 구조의 입출력 상태방정식 규명, 3) 산정된 등가지진하중과 규명된 입출력 상태방정식을 사용한 지진응답산정의 과정으로 구성된다. 제안된 기법은 유한요소기법(FEM) 모델 개선(Model Updating)에 기반한 지진응답예측기법에 비하여 모델링 오차가 개입 되지 않는 장점을 가진다. 캐비넷 구조를 이상화한 2차원 프레임 모델과 3차원 상세 모델에 대한 수치검증을 통하여 제안된 기법이 지진응답을 매우 정확하게 예측을 함을 관찰하였고, 측정 노이즈에 대해서도 강인함을 관찰하였다. 추후연구로 실험검증이 요구된다.

An emergency diesel generator(EDG) manufactured by a French company Wartsila SACM is a tandem type engine and consisted of two 10 cylindered diesel engines on each side. The maintenance manual provided by the manufacturer recommends that engine bearing be inspected every 15 years. However, it is difficult to inspect them because the manhole located in the lower compartment of the engine is too small for maintenance worker to access engine internals. Furthermore, the EDG should be disassembled and then overturned to inspect bearings unlike other EDG type. Such process will take longer period time than ordinary maintenance period. So it is not possible to inspect the main engine bearing and crank shaft during a routine or scheduled maintenance. In this paper, five methods are proposed and estimated to resolve the problem and the optimal maintenance method is chosen among them. The proposed optimal maintenance plan makes it possible to perform proper maintenance during regular maintenance period and to lower maintenance cost considerably.

The main objective of this paper is to search whether containment vessel's best pressure may increase until how long when loss of coolant accident (LOCA) happened in containment vessel of Ulchin nuclear power plant 1 and 2. Another goal of this research is to find the influential factors that increase containment vessel pressure. Model for this research is Ulchin nuclear power plant 1 with 10 cycles. Data were collected by simulator of Ulchin nuclear power plant 1 and design of experiment was used for data analysis. For the experiment, seven factors that are going to influence in containment vessel pressure were chosen. It was found that fatter which influences in early rise of containment vessel pressure after LOCA is only explosion size. Also, containment vessel's best pressure (3.74 bar.a) was much lower than limit (4.86 bar.a) of FSAR (Final Safety Analysis Report).

The Main Control Room(MCR) of Korean Next Generation Reactor(KNGR) has faced entirely new operation environment. The Computerized Procedure System(CPS) is completely different from existed Paper-based Procedure(PBP). The CPS which is improved by evaluation in this study is ready to be applied to the ergonomic foundations. In this study, we redesigned displays of the CPS as a Man-Machine Interface System(MMIS) to maximize human performance and to minimize human error and proposed an alternative display designs of the CPS applying principles related with MMIS.

지진취약도분석 기술은 원자력발전소의 구조물 및 기기의 실제 내진성능을 평가하기 위하여 이용된다. 이 논문에서는 원자력 발전소를 구성하는 구조물들의 지진취약도를 평가하는 개선된 기법에 대하여 요약하였다. 또한, 최근 몇 년간 한반도에서 발생된 소규모 기록지진의 응답스펙트럼에 대한 공학적 특성을 평가하고, 이러한 기록지진의 응답스펙트럼을 부지의 실제 지반운동으로 사용할 경우, 지진취약도 분석에 미치는 영향을 검토하였다. 몇가지 예제 구조물에 대한 지진취약도분석을 통하여 기록지진의 특성이 한국형 원자력발전소의 내진성능에 미치는 영향을 정량적으로 평가하였다. 평가결과, 현재까지 부지의 실제 지반운동으로 사용되어 오던 Newmark 스펙트럼은 국내 시설물의 내진성능을 과대평가 할 수 있음을 보여주었다.

본 논문에서는 오래된 원자력발전소의 내진검증과 관련한 USI A-46 문제의 해결에 사용될 수 있는 캐비닛의 내진보강방안에 대해 연구하였다. 캐비닛 구조물의 동적거동특성을 파악하기 위하여 3종류의 모델링을 수행하였고 그 결과를 비교하였다. 또한 ICRS(In Cabinet Reponse Spectrum)의 저감을 위하여 1) 보강프레임, 2)감쇠기 설치, 3) 동조질량감쇠기 등 세 가지 내진보강방안에 대하여 구조물의 응답을 산정하였다. 해석결과, 가새보강 및 감쇠기를 설치하는 보강방법에서는 보강전의 구조물보다 큰 ICRS가 얻어지는 경우가 발생해 보강시 많은 주의가 요구된다. 동조질량감쇠기의 사용은 좋은 제진효과를 보였으나 실구조물과 정확한 진동특성을 반영한 모델의 작성이 중요한 것으로 판단되었다.

SOC(Social Overhead Capital) projects such as road, power plant, airport or telecommunication facility construction require a large scale of cost, a long period of time and management of a number of sub-contractors. So systematic and efficient management tool in SOC projects is inevitable. Information system provides a valuable tool which can integrate and manage the large volume of information for SOC projects. This study investigates and analyzes the information system of nuclear power plant construction project. Based on this study, we can suggest the direction for designing information system for SOC projects.

최근 우리나라에서는 산업이 급속도로 발전하면서 급증하는 전력수요를 충당하기 위하여 원자력발전소의 건설과 가동이 증가 추세에 있다. 수년에 걸친 발전소의 건설 과정에서 부지의 매립과 준설은 저서 해조류의 서식처를 교란시키고 이는 나아가서 종조성의 변화를 야기한다. 발전소가 정상 가동하게 되면 필연적으로 다량의 온배수를 주변으로 방출하는데, 고착성 해조류는 수온의 상승에 민감하게 반응한다. 국내 원자력발전소에서는 냉각수가 복수기를 통과하면서 수온이 7~12