• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2709-2716
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• 2020

Compositions of large nuclear cores (e.g. boiling water reactors) are highly heterogeneous in terms of fuel composition, control rod insertions and flow regimes. For this reason, they usually lack high order of symmetry (e.g. 1/4, 1/8) making it difficult to estimate their neutronic parameters for large spaces of possible loading patterns. A detailed hyperparameter optimization technique (a combination of manual and Gaussian process search) is used to train and optimize deep neural networks for the prediction of three neutronic parameters for the Ringhals-1 BWR unit: power peaking factors (PPF), control rod bank level, and cycle length. Simulation data is generated based on half-symmetry using PARCS core simulator by shuffling a total of 196 assemblies. The results demonstrate a promising performance by the deep networks as acceptable mean absolute error values are found for the global maximum PPF (~0.2) and for the radially and axially averaged PPF (~0.05). The mean difference between targets and predictions for the control rod level is about 5% insertion depth. Lastly, cycle length labels are predicted with 82% accuracy. The results also demonstrate that 10,000 samples are adequate to capture about 80% of the high-dimensional space, with minor improvements found for larger number of samples. The promising findings of this work prove the ability of deep neural networks to resolve high dimensionality issues of large cores in the nuclear area.

• 농업생명과학연구
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• 제45권3호
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• pp.81-88
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• 2011

본 연구에서는 딸기의 냉장 및 상온 저장 시 일반세균, pH, color, firmness 등의 품질특성에 있어 염수 세척에 따른 영향을 분석하였다. 시료는 세척하지 않은 대조구, 염수세척 시료구, 염수세척 후 물기제거한 시료구 세 가지 종류로 준비하였다. 일반세균의 경우 염수세척 후 물기제거한 경우에 염수세척 시료구와 비세척 대조구에 비해 세균수가 저감화되었으며, 대수증식기가 나타나지 않았다. pH의 경우, 비세척 대조구와 염수세척 시료구에서는 다소 감소했으나, 염수세척 후 물기를 제거한 시료구에서는 거의 변화가 없는 것으로 나타났다. 적색도는 비세척 대조구와 염수세척 후 물기제거 시료구에서 저장기간이 경과함에 따라 증가되었으나, 염수세척 시료구에서는 감소되었다. 경도의 경우 $4^{\circ}C$에서 저장했을 때, 저장 간에 큰 변화를 보이지 않았다. 결론적으로 딸기를 염수세척하여 물기를 제거할 경우, 저장기간을 크게 연장할 수 있을 것으로 사료된다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2001년도 추계학술발표회요약집
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• pp.358.2-358
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• 2001

• Nuclear Engineering and Technology
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• 제44권3호
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• pp.311-322
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• 2012

Since the crisis at the Fukushima plants, severe accident progression during a station blackout accident in nuclear power plants is recognized as a very important area for accident management and emergency planning. The purpose of this study is to investigate the comparative characteristics of anticipated severe accident progression among the three typical types of nuclear reactors. A station blackout scenario, where all off-site power is lost and the diesel generators fail, is simulated as an initiating event of a severe accident sequence. In this study a comparative analysis was performed for typical pressurized water reactor (PWR), boiling water reactor (BWR), and pressurized heavy water reactor (PHWR). The study includes the summarization of design differences that would impact severe accident progressions, thermal hydraulic/severe accident phenomenological analysis during a station blackout initiated-severe accident; and an investigation of the core damage process, both within the reactor vessel before it fails and in the containment afterwards, and the resultant impact on the containment.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2004년도 추계학술대회 논문집
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• pp.948-953
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• 2004

For stable walking of various biped walking robots(BWR), we need to know the kinematics, dynamics and the Zero Moment of Point(ZMP) which are not easy to analyze analytically. In this reason, we developed a simulation program for BWRs composed of 4 degree-of-freedom upper-part body and 12 degree-of-freedom lower-part of the body. To operate the motion simulator for analyzing the kinematics and dynamics of BWES, inputs for the distance between legs, base angle, choice of walking type, gaits, and walking velocity are necessary. As a result, if stability condition is satisfied by the simulation, angle data for each actuator are generated automatically, and the data are transmitted to BWRS and then, they are actuated by the motion data. Finally, we validate the performance of the proposed motion simulator by applying it to a constructed small sized BWR.

• 원자력산업
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• 제5권11호통권33호
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• pp.56-65
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• 1985

다음은 미국 MIT원자력공학과의 Hansen 교수와 서독 베를린공과대학의 Winje교수가 공동으로 양국 원자력발전소의 가동실적(1980-1983년까지 년간)을 비교분석한 보고서의 내용이다. 대상으로한 원자로는 미국이 PWR(WH사제) 21기, BWR(GE사제) 22기이고, 서독측은 PWR(KWU사제)6기, BWR(동)4기인데 주요분석은 PWR에 중점을 두고 있으며(표1, 표2) 대상으로한 원자로는 (1) 출력 400MWe이상 (2) 1980년이전에 상업운전개시 (3) NSSS와 터빈$\cdot$발전기의 공급자가 동일이라는 기준으로 선택되어 있다. 가동실적의 비교로는 공통의 지표로 가동율(일정기간중의 발전량을 동기간중의 정격출력발전량으로 나눈 것)을 사용하고 있다. 그밖에 발전손실(정격출력발전량과 실제발전량의 차이)의 원인을 비교분석하여 양국 원전운전실적의 상위와 그 요인$\cdot$배경을 명백히 하려는 것이 연구의 개요이다.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2002년도 ICCAS
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• pp.105.6-105
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• 2002

Contents 1We developed a new type of lower part of the human-sized BWR (biped walking robot) driven by a new actuator based on the ball screw which has high strength and high gear ratio. Each leg of the robot is composed of three pitch Joints and one roll joint. In all, a 8 degree-of-freedom robot was developed. A new type of actuator for the robot is proposed, which is composed of four bar link mechanism driven by the ball screw. The BWR was designed to walk autonomously by adapting small DC motors for the robot actuators and has an embeded controller system including host computer, batteries and motor drivers. In the performance test, we had basic stable walking data so far, but we f...

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 1997년도 추계학술대회 논문집
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• pp.458-461
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• 1997

We have developed a human-sized BWR(biped walking robot) driven by a new actuator based on the ball screw which has high strength and high gar ratio. Each leg of the robot is composed of three pitch joints and one roll joint. In all, a 10 degree-of-freedom robot with two balancing joints was developed. For the purpose of autonomous walking and higher performance, we improved the previous developed BWR. We improved the motor drive efficiency, designed the ball screw actuator in a modular type, and simplified the electric wires. Through this modification, we achieved better performance in walking.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2887-2900
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• 2020

Cladding failure in a fuel rod during operation in a BWR is analyzed using a FALCON code-based model. Comparative calculation with a neighbouring, intact rod is presented, as well. A considerable 'hot spot' effect in cladding temperature is predicted with the SLICE-DO model due to a thermal barrier caused by the localized crud deposition. Particularly significant overheating is expected to occur on the affected side of the cladding of the failed rod, in agreement with signs of significant localized crud deposition as revealed by Post Irradiation Examination. Different possibilities (criteria) are checked, and Pellet-Cladding Mechanical Interaction (PCMI) is shown to be one of the plausible potential threats. It is shown that PCMI could lead to discernible concentrated inelastic deformation in the overheated part of the cladding. None of the specific mechanisms considered can be experimentally or analytically identified as an only cause of the rod failure. However, according to the current calculation, a possibility of cladding failure by PCMI cannot be excluded if the crud thickness exceeded 300 ㎛.

• 원자력산업
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• 제36권6호
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• pp.45-50
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• 2016

미국의 전력회사 Entergy는 향후 4년 내에 비등수형(BWR) 원자로 3기의 운영을 중단하고 영구 폐쇄에 들어갈 계획이다. 무엇 때문에 Entergy가 그런 조기 폐쇄 결정을 내리게 되었는지, 그리고 그러한 결정이 결과적으로 어떤 문제를 초래할 수 있는지 등에 대해 알아보고자 한다.