Dynamic responses of nuclear power plant structure subjected to earthquake loads should be carefully investigated for safety. Because nuclear power plant structure are usually constructed by material of reinforced concrete, the aging deterioration of R.C. have no small effect on structural behavior of nuclear power plant structure. Therefore, aging deterioration of R.C. nuclear power plant structure should be considered for exact prediction of seismic responses of the structure. In this study, a machine learning model for seismic response prediction of nuclear power plant structure was developed by considering aging deterioration. The OPR-1000 was selected as an example structure for numerical simulation. The OPR-1000 was originally designated as the Korean Standard Nuclear Power Plant (KSNP), and was re-designated as the OPR-1000 in 2005 for foreign sales. 500 artificial ground motions were generated based on site characteristics of Korea. Elastic modulus, damping ratio, poisson’s ratio and density were selected to consider material property variation due to aging deterioration. Six machine learning algorithms such as, Decision Tree (DT), Random Forest (RF), Support Vector Machine (SVM), K-Nearest Neighbor (KNN), Artificial Neural Networks (ANN), eXtreme Gradient Boosting (XGBoost), were used t o construct seispic response prediction model. 13 intensity measures and 4 material properties were used input parameters of the training database. Performance evaluation was performed using metrics like root mean square error, mean square error, mean absolute error, and coefficient of determination. The optimization of hyperparameters was achieved through k-fold cross-validation and grid search techniques. The analysis results show that neural networks present good prediction performance considering aging deterioration.

원자력발전소(원전) 내부에 설치되어 있는 주요 기기는 원전의 안정적인 운영을 돕는 주요 2차 구조 물이다. 경주 지진, 포항 지진과 같은 강한 지진이 발생하였을 때, 원전 주요 기기의 손상은 원전의 안정한 정지에 문제를 초래할 수 있다. 따라서, 원전 주요 기기의 지진응답을 저감시키기 위한 연구가 필수적으로 요구된다. 이러한 배경 아래, 본 연구에서는 원전 주요 기기의 내진성능 향상을 위하여 동 흡진장치(Dynamic Absorber)를 활용하였다. 연구에서 사용된 동흡진장치는 스프링, 댐퍼, 및 질량체로 구성된다. 이러한 동흡진장치를 설계하기 위하여 기존에 제안된 방법론들을 활용하였으며, 각 방법론 들을 기반으로 설계된 동흡진장치의 지진응답 저감효과를 비교 및 분석하였다. 구체적으로, 진동대 시 험 결과를 바탕으로 유한요소 모델을 검증하였다. 또한, 이를 기반으로 기존 동흡진장치의 설계방법론 에 따른 원전 주요 기기의 지진응답 저감 효과를 비교 및 분석하였다. 결과적으로 각 방법론들은 원전 주요기기의 가속도, 변위, 응력 응답을 평균적으로 약 30% 정도 감소시키는 효과를 보였다.

Tomatoes in greenhouse are a widely cultivated horticultural crop worldwide, accounting for high production and production value. When greenhouse ventilation is minimized during low temperature periods, CO2 enrichment is often used to increase tomato photosynthetic rate and yield. Plant-induced electrical signal (PIES) can be used as a technology to monitor changes in the biological response of crops due to environmental changes by using the principle of measuring the resistance value, or impedance, within the crop. This study was conducted to investigate the relationship between tomato growth data, vital response, and PIES resulting from CO2 enrichment in greenhouse tomatoes. The growth of tomato treated with CO2 enrichment in the morning was significantly better in all items except stem diameter compared to the control, and PIES values were also higher. The growth of tomato continuously applied with CO2 was better in the treatment groups than control, and there was no significant difference in chlorophyll fluorescence and photosynthesis. However, PIES and SPAD values were higher in the CO2 treatment group than control. CO2 enrichment have a direct relationship with PIES, growth increased, and transpiration increased due to the increased leaf area, resulting in increased water absorption, which appears to be reflected in PIES, which measures vascular impedance. Through this, this study suggests that PIES can be used to monitor crops due to environmental changes, and that PIES is a useful method for non-destructively and continuously monitoring changes of crops.

In assessing the seismic safety of nuclear power plants, it is essential to analyze the structures using the observed ground motion. In particular, spatial variation in which the characteristics of the ground motion record differ may occur if the location is different within the site and even if the same earthquake is experienced. This study analyzed the spatial variation characteristics of the ground motion observed at the structure and site using the earthquake records measured at the Hamaoka nuclear power plant. Even if they were located on the same floor within the same unit, there was a difference in response depending on the location. In addition, amplification was observed in Unit 5 compared to other units, which was due to the rock layer having a slower shear wave velocity than the surrounding bedrock. Significant differences were also found in the records of the structure’s foundation and the free-field surface. Based on these results, the necessity of considering spatial variation in the observed records was suggested.

The dynamic characterization of a three-story auxiliary building in a nuclear power plant (NPP) constructed with a monolithic reinforced concrete shear wall is investigated in this study. The shear wall is subjected to a joint-research, round-robin analysis organized by the Korea Atomic Energy Research Institute, South Korea, to predict seismic responses of that auxiliary building in NPP through a shake table test. Five different intensity measures of the base excitation are applied to the shaking table test to get the acceleration responses from the different building locations for one horizontal direction (front-back). Simultaneously to understand the global damage scenario of the structure, a frequency search test is conducted after each excitation. The primary motivation of this study is to develop a nonlinear numerical model considering the multi-layered shell element and compare it with the test result to validate through the modal parameter identification and floor responses. In addition, the acceleration amplification factor is evaluated to judge the dynamic behavior of the shear wall with the existing standard, thus providing theoretical support for engineering practice.

최근 국내에서 발생한 경주지진 및 포항지진이 도심지 및 원자력발전소 주변에서 발생함에 따라 인근 주요 구조시스 템에 피해를 발생시킨 바 있다. 이에 따라, 본 연구는 원전 배관계통의 지진 거동 특성을 실험 및 해석적으로 규명하고, 이를 바탕으로 내진성능을 평가하는 연구를 수행하는 것을 목적으로 한다. 이를 위하여, 원전 배관계통을 대상으로 한 진동대 시험 결과를 바탕으로 배관 수치해석 모델을 수립하고 이를 시험 결과를 통하여 검증한다. 또한, 이러한 검증된 수치해석모델을 기반으로 배관계통의 내진성능을 평가한다. 수치해석 모델 검증 결과, 수립된 수치모델의 고유진동수, 감쇠비 및 변위 응답이 진동 대시험 결과와 유사한 것으로 나타났다. 이러한 검증된 수치모델을 바탕으로 평가된 내진성능 값은 기존 원전 배관의 내진성능 값의 범위와 비교적 유사한 값으로 평가되었다. 이는 설계기준지진을 크게 상회하는 값이지만, 원전 주요 기기 임을 감안할 때 추가적인 내진성능 상향이 확보되면 원전 지진 안전성 향상에 많은 기여를 할 수 있을 것으로 판단된다. 본 연구의 결과는 추후 원전 배관계통 내진성능평가를 위한 정량적인 자료로 활용이 가능할 것으로 판단된다.

The pea aphid, Acyrthosiphon pisum, requires the nutritional endosymbiont, Buchnera, for the production of essential amino acids. However, it is unclear if host plant diet that varies in essential amino acids influences aphid regulation of its nutritional symbioses. We hypothesized that aphid genes respond to host plant diet when aphids feed on their specialized (alfalfa) compared to universal host plant diet (fava), which vary in essential amino acid concentrations. Using RNA-Seq and whole genome bisulfite sequencing, we compared the gene expression profiles and DNA methylation distributions of specialized aphid cells that harbor Buchnera (bacteriocytes) when aphids feed on their specialized compared to their universal host plant diets. Our results show that bacteriocyte transcription and methylation patterns differ between host plant diets. When aphids feed on their specialized host plant, they significantly up-regulate and/or hypo-methylate key aphid genes in bacteriocytes related to the amino acid metabolism, including glutamine synthetase (GS) and the glutamine transporter ApGLNT1. Moreover, regardless of which host plant aphids feed on, we observed significant up-regulation and differential methylation of the key genes in the amino acid metabolism and the glycine/serine metabolism in aphid bacteriocytes. We suggest that the regulatory response of key symbiosis genes in bacteriocytes allows aphids to feed on a specialized host plant diet with suboptimal nitrogen concentrations.

The probabilistic seismic safety assessment is one of the methodology to evaluate the seismic safety of the nuclear power plants. The site characteristics of the nuclear power plant should be reflected when evaluating the seismic safety of the nuclear power plant. The Korea seismic characteristics are strong in high frequency region and may be different from NRC Regulatory Guide 1.60, which is the design spectrum of nuclear power plants. In this study, seismic response of a nuclear power plant structure by Pohang earthquake (2017.11.15. (KST)) is investigated. The Pohang earthquake measured at the Cheongsong seismic observation station (CHS) is scaled to the peak ground acceleration (PGA) of 0.2 g and the seismic acceleration time history curve corresponding to the design spectrum is created. A nuclear power plant of the containment building and the auxiliary buildings are modeled using OPENSEES to analyze the seismic response of the Pohang earthquake. The seismic behavior of the nuclear power plant due to the Pohang earthquake is investigated. And the seismic performances of the equipment of a nuclear power plant are evaluated by the HCLPF. As a result, the seismic safety evaluation of nuclear power plants should be evaluated based on site-specific characteristics of nuclear power plants.

The seismically isolated nuclear power plants shall be designed for design basis earthquake (DBE) and considered to ensure safety against beyond design basis earthquake (BDBE). In order to limit the excessive displacement of the seismic isolation system of the seismically isolated structure, the moat is installed at a certain distance from the upper mat supporting the superstructure. This certain distance is called clearance to stop (CS) and is calculated from the 90th percentile displacement of seismic isolation system subjected to BDBE. For design purposes, the CS can be obtained simply by multiplying the median displacement of the seismic isolation system against DBE by scale factor with a value of 3. The DBE and BDBE used in this study were generated by using 30 sets of artificial earthquakes corresponding to the nuclear standard design spectrum. In addition, latin hyper cube sampling was applied to generate 30 sets of artificial earthquakes corresponding to maximum - minimum spectra. For the DBE, the median displacement and the 99th percentile displacement of the seismic isolation system were calculated. For the BDBE, the suitability of the scale factor was assessed after calculating the 90th percentile displacement of the seismic isolation system.

In order to improve the seismic performance of structures, friction pendulum system (FPS) is the most commonly used seismic isolation device in addition to lead rubber bearing (LRB) in high seismicity area. In a nuclear power plant (NPP) with a large self weight, it is necessary to install a large number of seismic isolation devices, and the position of the center of rigidity varies depending on the arrangement of the seismic isolation devices. Due to the increase in the eccentricity, which is the difference between the center of gravity of the nuclear structure and the center of stiffness of the seismic isolators, an excessive seismic response may occur which could not be considered at the design stage. Three different types of eccentricity models (CASE 1, CASE 2, and CASE 3) were used for seismic response evaluation of seismically isolated NPP due to the increase of eccentricity (0%, 5%, 10%, 15%). The analytical model of the seismic isolation system was compared using the equivalent linear model and the bilinear model. From the results of the seismic response of the seismically isolated NPP with increasing eccentricity, it can be observed that the effect of eccentricity on the seismic response for the equivalent linear model is larger than that for the bilinear model.

CO2농도와 온도의 상승으로 인한 지구온난화가 진행되었을 때 광, 수분 그리고 유기물 구배에 따른 멸종위기식물인 황근의 생육과 생태적 지위폭의 변화를 알아보았다. 대조구(야외)와 처리구(CO2 + 온도 상승구)로 나누어 각각 광, 수분 그리고 유기물구배를 두어 재배하였다. 그 연구결과, 황근은 낮은 광량보다 높은 광량을 선호하나, 광량이 787±77.76μmol m-2s-1을 넘어가면 높은 광량이라 하더라도 생육이 어려웠다. 또한 유기물이 없거나(0%) 너무 많은 토양(20%)에서는 생육이 어려웠다. 그러나 수분 구배에 따른 경향이 보이지 않았다. 황근의 고사율은 대조구보다 처리구에서 광량이 높은 조건을 제외한 모든 구배에서 높았다. 이는 CO2와 온도가 상승하면 광에 대한 내성범위가 좁아진다는 것을 의미한다. 대조구와 처리구를 비교하였을 때, 수분구배에 따른 경향은 보이지 않았다. 유기물구배에서 는 대조구보다 처리구에서 모두 고사율이 낮았는데, 이는 유기물에 대한 내성의 범위가 넓어진 것을 의미한다. 황근의 생태적 지위폭은 처리구가 대조구보다 광 구배에서 30.1% 좁아졌으며, 수분 구배에서 8.6% 그리고 유기물 구배에서 30% 넓어졌다. 따라서 CO2농도와 온도의 증가로 인한 지구온난화가 진행되면, 황근의 생육은 광량에 의해서 제한될 것으로 판단된다.

The purpose of this study is to investigate the response of the soil mesofauna and ground-dwelling arthropods to vegetation structure and composition in a mountain pasture. The pasture mainly comprised five types of plant communities; Agrostis alba - Phleum pratense community, Poa pratensis community, Festuca ovina community, Rumex acetosella community, and the shrub assemblage comprised Spiraea miyabei-Spiraea salicifolia community. Soil chemical properties including the pH, EC and nutrient levels were influenced by plant communities. Plant-specific responses were observed for bacteria-feeding and plant-feeding soil nematodes. Collembola and Oribatida having the same feeding habit were influenced differently by plants. nMDS showed that the community of ground-dwelling arthropods were separated by vegetation types. Species numbers of arthropods were different among different plant communities. Our results indicate that vegetation structure and composition can influence both abundance of diversity of terrestrial fauna.

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.

본 연구에서는 한국 멸종위기식물인 분홍장구채의 보전 및 인공재배를 위해 식물공장 내 인공적인 광 조건에서 일어나는 생리와 개화반응 특성을 알아보았다. 이를 위해 분홍장구채를 식물공장의 각 챔버에 적색광, 청색광, 백색광, 적색+원적색 혼합광, 적색+청색 혼합광 그리고 적색+청색+백색 혼합광 하에서 재배하여 광합성률, 증산률, 기공전도도, 수분이용효율, 엽록소함량, 최소엽록소형광, 최대엽록소형광, 광계II의 광화학적 효율 그리고 잎과 꽃 수를 측정하였다. 그 결과 적색 단일광과 적색+원적색 혼합광에서 분홍장구채는 가장 많이 개화하였으며, 이 광조건에서는 광합성률, 증산률 그리고 기공전도도는 상대적으로 다른 조건보다 높았으나 수분이용효율은 차이가 없었으며, 엽록소함량은 적었 다. 특히 최소 및 최대 엽록소형광과 광계II의 광화학적 효율은 적색 단일광 조건에서 다른 광 조건보다 낮았다. 이러한 결과는 분홍장구채의 꽃의 생산을 위해서는 적색 단일광이나 적색+원적색의 인공광 조건에서 재배하는 것이 효율적이 라는 것을 의미한다.

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.