The Auxiliary Building Controlled Area Emergency Exhaust Air Cleaning Units (ACU) should be taken into account in the accident analysis that the entire gaseous radioactive material is exhausted to the environment through the auxiliary building without any filtration until the pressure reaches a negative pressure, approximately -0.25 inch, water gauge, when the ACU operation is credited in the analysis. Thus, this paper performed thermal-hydraulic analysis using GOTHIC program and showed the exhaust flow from each room in the auxiliary building controlled area to maintain room pressure not greater than (-) 0.25 inch water gauge.

In order to modeling seismic isolation system such as lead-rubber bearing (LRB), bilinear model is widely used by many researchers. In general, an actual force-displacement relationship for LRB has a smooth hysteretic shape. So, Bouc-Wen model with smooth hysteretic shape represents more accurately actual hysteretic shape than bilinear model. In this study, seismic responses for seismically isolated nuclear power plant (NPP) with LRB modelled by Bouc-Wen and bilinear models are compared with those of NPP without seismic isolation system. To evaluate effect of earthquake characteristics for seismic responses of NPP isolated by LRB, 5 different site class earthquakes distinguished by Geomatrix 3rd Letter Site Classification and artificially generated earthquakes corresponding to standard design spectrum by Reg. Guide 1.60 are used as input earthquakes. From the seismic response results of seismically isolated NPP, it can be observed that maximum displacements of seismic isolation modelled by Bouc-Wen model are larger than those by bilinear model. Seismic responses of NPP with LRB is significantly reduced than those without LRB. This reduction effect for seismic responses of NPP subjected to Site A (rock) earthquakes is larger than that to Site E (soft soil) earthquakes.

The Gyeong-Ju earthquake in the magnitude of 5.8 on the Richter scaleoccurred in September 12, 2016. Because there are many nuclear power plants (NPP) near the epicenter of the Gyeong-Ju earthquake, the seismic stability of nuclear power plants is becoming a social problem. In order to evaluate the safety of seismically isolated NPP, the seismic response of a NPP subjected to the Gyeong-Ju earthquake was compared with those of 30 sets of artificial earthquakes corresponding to the nuclear standard design spectrum (NSDS). A 2-node model and a simple beam-stick model were used for the seismic analysis of seismically isolated NPP structures. Using 2-node model, the effect of internal temperature rise, decrease of shear stiffness, increase of lateral displacement and decrease of vertical stiffness according to nonlinear behavior of lead-rubber bearing (LRB) were evaluated. The displacement response, the acceleration response, and the shear force response of the seismically isolated nuclear containment structure were evaluated using the simple beam-stick model. It can be observed that the seismic responses of the isolated nuclear structure subjected to Gyeong-Ju earthquake is significantly less than those to the artificial earthquakes corresponding to NSDS.

This study intends to evaluate the conservativeness of the fixed-base analysis as compared to the soil-structure interaction (SSI) analysis for the seismically isolated model of a nuclear power plant in Korea. To that goal, the boundary reaction method (BRM), combining frequency-domain and time-domain analyses in a twofold process, is adopted for the SSI analysis considering the nonlinearity of the seismic base isolation. The program KIESSI-3D is used for computing the reaction forces in the frequency domain and the program MIDAS/Civil is applied for the nonlinear time-domain analysis. The BRM numerical model is verified by comparing the results of the frequency-domain analysis and time-domain analysis for the soil-structure system with an equivalent linear base isolation model. Moreover, the displacement response of the base isolation and the horizontal response at the top of the structure obtained by the nonlinear SSI analysis using BRM are compared with those obtained by the fixed-base analysis. The comparison reveals that the fixed-base analysis provides conservative peak deformation for the base isolation but is not particularly conservative in term of the floor response spectrum of the superstructure.

후쿠시마 원전사고 이후 광역의 방사성 오염부지가 발생되었으며, 이에 대한 제염작업으로 인하여 다량의 제염폐기물이 발 생하였다. 일본에서는 이를 보관하기 위하여 각 지역에 임시저장시설이 운영되고 있으며, 이들 시설들은 피난지시해제가 이루어진 지역의 일반인에 대하여 방사선학적 영향을 미칠 것으로 판단된다. 본 연구에서는 임시저장시설 인근에 거주하 는 일반인의 방사선학적 안전성 확보를 위하여 임시저장시설 특성에 따른 거리별 공간 방사선량률 및 선량제한치를 만족하 는 임시저장시설로부터의 이격거리를 평가하였다. 이를 위해 임시저장시설의 형태 및 크기, 복토 두께 등을 고려하였으며, MCNPX를 이용하여 방사선량률을 평가하였다. 복토에 의한 차폐효과는 두께가 10 cm일 때 68.9%, 30 cm일 때 96.9%, 50 cm 일 때 99.7%로 나타났다. 임시저장시설 형태에 따른 공간 방사선량률은 지상 보관형일 때 가장 높게 나타났으며, 이어서 반 지하 보관형, 지하 보관형일 순으로 나타났다. 임시저장시설 크기에 따른 공간 방사선량률은 5 × 5 × 2 m 시설을 제외한 시 설에 대하여 유사하게 나타났다. 이는 임시저장시설 내 적재된 제염폐기물에 의하여 자기차폐가 이루어지기 때문이다. 최종 적으로 크기가 50 × 50 × 2 m이고, 복토가 없는 임시저장시설의 경우, 지상 보관형의 평가된 이격거리는 14 m(최소농도), 33 m(최빈농도), 57 m(최대농도)이며, 반지하 보관형의 이격거리는 9 m(최소농도), 24 m(최빈농도), 45 m(최대농도), 지하 보관형의 이격거리는 6 m(최소농도), 16 m(최빈농도), 31 m(최대농도)로 나타났다.

Recently, many people have become interested in seismic stability enhancement and a chain of research and development be proceed for application of nuclear power plant according to increase the frequency and magnitude of earthquake event. Such as seismic isolation system is applied to general structure (architecture, bridge and LNG tank etc.) from ancient times. But the application results is limited for Nuclear power plant. In this paper, we proposed a stability of variable axial load from beyond design basis earthquake in Nuclear power plant. Also, the change of stiffness in isolator from the application of generally design equation is not equal to according to change in axial load compare with the experimental result in variable axial load. Therefore we proposed the empirical formula of design equation from test result of full-scale multi-lead rubber bearing for seismic analysis with real behavior (variable axial load) in the earthquake motion.

The Eradi Quake System (EQS) is a seismic isolation bearing system designed to minimize forces and displacements experienced by structures subjected to ground motion. The EQS dissipates seismic energy through friction of Poly Tetra Fluoro Ethylene (PTFE) disk pad. In general, a force-displacement relationship of EQS has post yield stiffness hardening during large inelastic displacement. In this study, seismic responses of seismically isolated nuclear power plant (NPP) subjected to design basis earthquake (DBE) and beyond design basis earthquakes (150% DBE and 167% DBE) are compared considering the post yield stiffness hardening effect of EQS. From the results, it can be observed that if the post-yield stiffness hardening effect of EQS is increased, the displacement response of EQS is reduced, and the acceleration and shear responses of containment structures of NPP is increased.

대규모 지진에 대한 원전의 안전성을 확보하는 방안으로 기존 원전 구조물에 면진장치를 설치하는 방안이 도입되고 있다. 면진장치를 설치함으로써 상부구조와 지반의 거동을 격리시킬 수 있고, 구조물 자체의 고유주기가 길어지게 되는데, 이를 통 해 지진하중에 대한 구조물의 응답을 감소시킬 수 있게 된다. 특히 원전구조물 설계 시 원전구조물 자체뿐만 아니라 원전 내 부 기기에 대한 안전성 확보가 필수적이다. 이를 위해 특정 층에 위치한 기기의 설계를 위해 각 층의 최대 요구 응답을 나타 내는 층응답스펙트럼이 일반적으로 사용된다. 본 논문에서는 원전 구조물의 지진해석을 통해 특정 층의 층응답스펙트럼을 평가하고, 면진 장치의 거동 특성중 하나인 2차 경화에 대한 영향 또한 평가하였다.

대규모 지진에 대한 원전의 안전성을 확보하는 방안으로 기존 원전 구조물에 면진장치를 설치하는 방안이 도입되고 있다. 면진장치를 설치함으로써 상부구조와 지반의 거동을 격리시킬 수 있고, 구조물 자체의 고유주기가 길어지게 되는데, 이를 통해 지진하중에 대한 구조물의 응답을 감소시킬 수 있게 된다. 특히 원전구조물 설계 시 원전구조물 자체뿐만 아니라 원전 내부 기기에 대한 안전성 확보가 필수적이다. 이를 위해 특정 층에 위치한 기기의 설계를 위해 각 층의 최대 요구 응답을 나타내는 층응답스펙트럼이 일반적으로 사용된다. 본 논문에서는 원전 구조물의 지진해석을 통해 특정 층의 층응답스펙트럼을 평가하고, 면진 장치의 거동 특성중 하나인 2차 경화에 대한 영향 또한 평가하였다.

본 연구에서는 항 내부에서 부하되는 오염물질이 파랑 및 흐름 조건으로 인하여 항외로 유출되는 과정을 수리실험을 통해 알아보았다. 월성원자력발전소 항내에 오염물질이 부하 되었을 시, 실험인자를 변화시켜가며 추적자를 활용한 흐름거동 조 사를 수행하였다. 각 실험의 결과는 지수 함수에 따른 항내 오염물이 감소하는 경향이 나타나며, 항외 유출에 걸리는 시간의 기울기는 각각 다른 결과를 보여주었다. 관측된 데이터로부터 회귀식을 도출한 결과, 흐름 관측의 경우 유입되는 모터의 회 전 속도 30, 20, 10 rpm에서 좌측 항내의 오염물이 50% 유출률에 도달하는 시간은 각각 2.70, 10.40, 26.39 days를 보였다. 모터의 회전속도가 30 rpm인 실험에서 유출되는 감소 추세가 가장 뚜렷하게 나타났으며, 회전속도 10 rpm인 실험에서 기 울기는 완만하였다. 파랑 관측의 우측 영역의 오염물이 50% 유출률에 도달하는 시간은 4.59 days로 나타났으며, 좌측영역 의 경우 15.35 days의 결과를 보였다.

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.

In order to increase seismic performance of nuclear power plant (NPP) in strong seismic zone, lead-rubber bearing (LRB) can be applied to seismic isolation system of NPP structures. Simple equivalent linear model as structural analysis model of LRB is more widely used in initial design process of LRB than a bilinear model. Seismic responses for seismically isolated NPP containment structures subjected to earthquakes categorized into 5 different soil-site classes are calculated by both of the equivalent linear- and bilinear- LRB models and compared each others. It can be observed that the maximum displacements of LRB and shear forces of containment in the case of the equivalent linear LRB model are larger than those in the case of bilinear LRB model. From the seismic fragility curves of NPP containment structures isolated by LRB, it can be observed that seismic fragility in the case of equivalent linear LRB model are about 5~30 % larger than those in the case of bilinear LRB model.

GRP pipe (Glass-fiber Reinforced Plastic Pipe) lines making use of FRP (Fiber Reinforced Plastic) are generally thinner, lighter, and stronger than the existing concrete or steel pipe lines, and it is excellent in stiffness/strength per unit weight. In this study, we present the result of field test for buried GRP pipes with large diameter(2,400mm). The vertical and horizontal ring deflections are measured for 387 days. The short-term deflection measured by the field test is compared with the result predicted by the Iowa formula. In addition, the long-term ring deflection is predicted by using the procedure suggested in ASTM D 5365(ANNEX) in the range of 40 to 60 years of service life of the pipe based on the experimental results. From the study, it was found that the long-term vertical and horizontal ring deflection up to 60 years is less than the 5% ring deflection limitation.

It is very important to assure the seismic performance of equipment as well as building structures in seismic design of nuclear power plant(NPP). Seismically isolated structures may be reviewed mainly on the horizontal seismic responses. Considering the equipment installed in the NPP, the vertical earthquake responses of the structure also should be reviewed. This study has investigated the vertical seismic demand of seismically isolated structure by lead rubber bearings(LRBs). For the numerical evaluation of seismic demand of the base isolated NPP, the Korean standard nuclear power plant (APR1400) is modeled as 4 different models, which are supported by LRBs to have 4 different horizontal target periods. Two real earthquake records and artificially generated input motions have been used as inputs for earthquake analyses. For the study, the vertical floor response spectra(FRS) were generated at the major points of the structure. As a results, the vertical seismic responses of horizontally isolated structure have largely increased due to flexibility of elastomeric isolator. The vertical stiffness of the bearings are more carefully considered in the seismic design of the base-isolated NPPs which have the various equipment inside.

This study investigated the influence of probabilistic variability in stiffness and nonlinearity of soil on response of nuclear power plant (NPP) structure subjected to seismic loads considering the soil-structure interaction (SSI). Both deterministic and probabilistic methods have been employed to evaluate the dynamic responses of the structure. For the deterministic method, SRPmin method given in USNRC SRP 3.7.2(2013) (envelope of responses using three shear modulus profiles of lower bound(GLB), best estimate(GBE) and upper bound(GUB)) and SRPmax method (envelope of responses by more than three ground profiles within range of GLB≤G≤GUB) have been considered. The probabilistic method uses the Latin Hypercube Sampling (LHS) that can capture probabilistic feature of soil stiffness defined by the median and the standard deviation. These analysis results indicated that 1) number of samples shall be larger than 60 to apply the probabilistic approach in SSI analysis and 2) in-structure response spectra using equivalent linear soil profiles considering the nonlinear behavior of soil medium can be larger than those based on low-strain soil profiles.

This paper presents a detailed procedure for a nonlinear soil-structure interaction of a seismically isolated NPP(Nuclear Power Plant) structure using the boundary reaction method (BRM). The BRM offers a two-step method as follows: (1) the calculation of boundary reaction forces in the frequency domain on an interface of linear and nonlinear regions, (2) solving the wave radiation problem subjected to the boundary reaction forces in the time domain. For the purpose of calculating the boundary reaction forces at the base of the isolator, the KIESSI-3D program is employed in this study to solve soil-foundation interaction problem subjected to vertically incident seismic waves. Wave radiation analysis is also employed, in which the nonlinear structure and the linear soil region are modeled by finite elements and energy absorbing elements on the outer model boundary using a general purpose nonlinear FE program. In this study, the MIDAS/Civil program is employed for modeling the wave radiation problem. In order to absorb the outgoing elastic waves to the unbounded soil region, spring and viscous-damper elements are used at the outer FE boundary. The BRM technique utilizing KIESSI-3D and MIDAS/Civil programs is verified using a linear soil-structure analysis problem. Finally the method is applied to nonlinear seismic analysis of a base-isolated NPP structure. The results show that BRM can effectively be applied to nonlinear soil-structure interaction problems.

This paper presents the performance improvement of an EQS (Eradic Quake System) device applied to a nuclear power plant. For the nuclear facility, the EQS device needs to be ensured to have high quality, flexibility of design and reliability. To improve the reliability of the design, the hysteresis of the device must be exactly predicted. The friction coefficient of PTFE (PolyTetraFluoroEthylene) and the stiffness of the MER-Spring are considered as the factors influencing the hysteresis curve. In this paper, those factors are analysed to predict the behavior of the device and to improve the equipment of the EQS device. The results of the improved EQS device have been verified via a tests to be comparable with the predicted results. The estimation results indicate that considering those factors is more appropriate than the results of the previous design and method.

원전의 항공기 충돌 리스크 평가에 사용되는 대표매개변수를 선정하기 위한 방법론을 개발하였다. 대상 원전은 국내의 대표적인 경수로형 원전 중 하나로 선정하여 3차원 유한요소 해석 모델을 구축하였다. 콘크리트 재료모델에는 소성손상모델이 적용되었으며, 강재는 다중선형곡선거동을 가지는 것으로 모델링하였다. 운동에너지, 전체 충격량, 최대 충격량, 최대 하중 등 4종의 대표매개변수 후보군을 선정하였다. 각각의 매개변수 후보군은 모두 충돌 속도와 질량의 함수로 표현되므로, 충돌속도 50~200m/s, 항공유량 30~90%의 범위에 대하여 매개변수값을 도출하고 충돌 해석을 수행하여, 충돌 시의 구조 응답과의 상관관계를 분석하였다. 모든 해석에서 항공기의 기종은 보잉767 기종으로 선정하였다. 충돌해석에는 Riera의 하중-시간이력 함수를 이용한 해석기법을 적용하였다. 매개변수와 충돌 시 응답의 상관관계 적합성은 결정계수값을 이용하여 분석하였다. 4 종의 대표매개변수 후보군 중 최대 하중값이 가장 직관적일 뿐만 아니라 본 연구에서의 해석 케이스에서는 응답과의 상관성도 가장 뛰어난 것으로 나타남에 따라, 항공기충돌 리스크 평가를 위하여 가장 적합한 매개변수라 할 수 있을 것으로 판단되었다.