• Proceedings of the Korean Information Science Society Conference
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• 2001.04a
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• pp.586-588
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• 2001

원전보호계통(RPS: Reactor Protection System)은 사고 시 치명적 피해를 입을 수 있다는 점에서 안전에 대한 중요도가 가장 높은 Safety 1E class로 분류되며, 이러한 보호계통을 디지털 라이즈 하는데 있어서 높은 신뢰도에 대한 보장이 필요하다. 따라서 본 논문에서는 DPPS(Digital Plant Protection System) 내에서 작동하는 내장형 소프트웨어의 높은 신뢰성을 보장하기 위한 테스팅 방법론을 제시하고자 한다. DPPS에서 작동하는 내장형 소프트웨어를 테스트하기 위한 방법은 크게 두 가지로 나누어진다. 첫 번째 단계는 절차중심의 프로그램에서 객체를 추출하고 이를 이용하여 클래스를 추출하는 제공학의 단계이다. 두 번째 단계는 이러한 클래스들을 이용하여 레벨별 테스팅을 수행하기 위한 테스트 아이템을 추출하고, 추출된 테스트 아이템을 이용하여 테스트 케이스를 선정하는 단계이다. 이렇게 각 레벨별로 선정된 테스트 케이스를 이용하여 단위 테스팅, 통합 테스팅, 시스템 테스팅 이렇게 3단계의 레벨별 테스팅을 수행한다.

• Proceedings of the IEEK Conference
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• 2003.07a
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• pp.589-592
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• 2003

원자로보호계통은 비정상운전으로부터 원자로를 보호하기 위해 안전센서 신호를 감시하고, 그 값이 트립 설정치를 초과할 경우 자동으로 원자로 트립 또는/및 공학적 안전설비 작동 신호를 개시한다. 따라서, 원자로 보호계통은 4개의 채널로 구성되며, 각 채널간 및 채널내에서는 데이터 통신망을 통해 원자로 트립신호와 운전정보를 전송한다. 이러한 기능을 수행하는 데이터 통신망은 실시간 및 결정론적 프로토콜을 만족해야 한다. 특히, 원자로 트립신호를 전송하는 안전등급 통신망은 채널간 격리 및 브로드 캐스팅(Broadcasting) 요건을 만족해야 한다. 본 논문에서는 원자로보호계통에 적용되는 데이터 통신망 설계기준과 프로토콜 설계방안에 대해 기술한다.

• Journal of Korean Society on Water Environment
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• v.22 no.2
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• pp.300-307
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• 2006

The combined SHARON (Single reactor system for High ammonium Removal Over Nitrite)-ANAMMOX (Anaerobic ammonium oxidation) reactor were operated in mesophilic condition ($35^{\circ}C$). In this study, microbial granulation and characteristics of SHARON and ANAMMOX sludges were investigated using settling test, Scanning Electron Microscopy (SEM) and Fluorescence In Situ Hybridization (FISH). In SHARON reactor, Aerobic granulation with diameter of 1.5~2.5 mm was accomplished but aerobic granulation was weaker than anaerobic granular sludge. Initial seed sludge of ANAMMOX reactor was used as attached media for biofilm growth. ANAMMOX sludge was more compact and rounder rather than seed sludge. Though ANAMMOX sludge has high activity, it has lower settling ability than the seed granule. The color of ANAMMOX sludge was changed from dark to redish brown granular with diameter of 1~2 mm. In FISH of ANAMMOX sludge, high fraction of Candidatus B. stuttgartiensis which paid great role of nitrogen conversion was detected. Also, FISH results reveals that ANAMMOX bacteria inhabit at inner parts near surface, having advantages in utilization of substrates and protection from oxygen inhibition.

• 한국신재생에너지학회:학술대회논문집
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• 2006.06a
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• pp.37-42
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• 2006

In this study, $20Nm^3/hr$ scale compact hydrogen generator which can be apply to the hydrogen station was tested for hydrogen station application. $20Nm^3/hr$ scale compact hydrogen generator was developed by upgrading concept of stacking plate reactor from former $20Nm^3/hr$ scale plate hydrogen generator. concepts for improving system efficiency and performance include such as idea of heat recovery from the exhaust, exhaust duct which is especially design for plate type reactor reinforcement of insulation, enlargement of heat exchange area of reactor, introduction of desulphurizer reactor and PROX rector in a compact design, introduction of back fire protection structure of plate burner and so on, We can learn that final prototype of scale-up $20Nm^3/hr$ scale compact hydrogen generator can be operated steadily in 100% road at which over 94% of methane conversion(S/C=3.75) was obtained. In case of making up the weak point, we expect that it is possible to apply to hydrogen station by way of showing an example.

• Nuclear Engineering and Technology
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• v.44 no.7
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• pp.799-806
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• 2012

In recent years, a new algorithm has been introduced to perform the regional overpower protection (ROP) detector layout optimization for $CANDU^{(R)}$ reactors. This algorithm is called DETPLASA. This algorithm has been shown to successfully come up with a detector layout which meets the target trip set point (TSP) value. Knowing that these ROP detectors are placed in a number of safety channels, one expects that there is an optimal placement of the candidate detectors into these channels. The objective of the present paper is to show that a slight improvement to the TSP value can be realized by optimizing the channelization of these ROP detectors. Depending on the size of the ROP system, based on numerical experiments performed in this study, the range of additional TSP improvement is from 0.16%FP (full power) to 0.56%FP.

• Journal of Radiation Protection and Research
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• v.41 no.4
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• pp.373-377
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• 2016

Background: Experiments with small electrochemical apparatus were previously carried out for detecting low-energy neutrinos under irradiation of reactor neutrinos and under natural neutrino environment. The experimental result indicated that the output current of reactor-neutrino irradiated detector was appreciably larger than that of natural environmental one. Usual interaction cross-sections of neutrinos are quite small, so that they do not explain the experimental result at all. Materials and Methods: To understand the experimental data, we propose that some biological products may generate AV-type scalar field B0, leading to a large interaction cross-section. The output current generation is ascribed to an electrochemical process that may be assisted by weak interaction phenomena. Dissolved oxygen concentrations in the detector solution were measured in this study, for the purpose of understanding the mechanism of the detector output current generation. Results and Discussion: It was found that the time evolution of experimental output current was mostly reproduced in simulation calculation on the basis of the measured dissolved oxygen concentration. Conclusion: We mostly explained the variation of experimental data by using the electrochemical half-cell analysis model based on the DO concentration that is consistent to the experiment.

• Nuclear Engineering and Technology
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• v.56 no.2
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• pp.498-505
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• 2024

In this paper, a cable-driven endoscopic manipulator (CEM) is designed for the Chinese latest compact fusion reactor. The whole CEM arm is more than 3000 mm long and includes end vision tools, an endoscopic manipulator/control system, a feeding system, a drag chain system, support systems, a neutron shield door, etc. It can cover a range of ±45° of the vacuum chamber by working in a wrap-around mode, etc., to meet the need for observation at any position and angle. By placing all drive motors in the end drive box via a cable drive, cooling, and radiation protection of the entire robot can be facilitated. To address the CEM motion control problem, a discrete trajectory tracking method is proposed. By restricting each joint of the CEM to the target curve through segmental fitting, the trajectory tracking control is completed. To avoid the joint rotation angle overrun, a joint limit rotation angle optimization method is proposed based on the equivalent rod length principle. Finally, the CEM simulation system is established. The rationality of the structure design and the effectiveness of the motion control algorithm are verified by the simulation.

• Proceedings of the KIEE Conference
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• 2006.05a
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• pp.48-50
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• 2006

SC(Static Condenser) in KEPCO is used in voltage control and power factor compensation. Currently KEPCO uses SC to 154kv 50MVA and 23kv SMVA. It is not important in old days because a SC bank accident has no effect on power system. But we are interested in the SC bank for power quality in these days. The SC Bank has a reactor and a condenser using series connection. It is operated in critical point for resonance circuit normally. Therefore the SC bank has a small reliability against other Power instruments. If a 4th harmonic frequency as a resonance frequency is supplied in system, the condenser is damaged because of a resonance current. And a trip and a closing for CB(Circuit Breaker) in many times will have a big influence of SC bank destruction. General OCR(Over Current Relay) observing SC bank is not useful for this protection We think that protection relay must be have the SC bank characteristics. A solution for this problem is active Power, resonance frequency and impedance.

• Fire Science and Engineering
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• v.25 no.5
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• pp.54-61
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• 2011

The study is to analysis of fire protection regulations for the nuclear power plants (NPP) in the United States, Japan, the UAE (United Arab Emirates), and Korea with the intention of exporting NPP to the UAE. Fire protection regulations for NPP for these countries permit the fire protection design and facilities in accordance with the evaluation of the potential fire hazards. However, in Korea, the NPP is a part of power generation facilities in Korea fire protection law, and the atomic energy act classifies them as the reactor and related nuclear facilities. The fire protection law and atomic energy act are different to the criteria for the fire protection of NPP. To maintain the leading position as a nuclear exporting country, the performance-based fire hazard analysis should be reasonably incorporated in the design of the fire protection system. It was suggested that the integrated requirements of the fire protection for NPP should be incorporated to the construction article for the fire protection facilities specified in paragraph 2 of Act II, being classified into the special objects to be protected against fire, which requires a performance-based design in order to incorporate the specific requirements for NPP.

• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 2000.11a
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• pp.111-114
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• 2000

본 논문은 선형모델의 모델 계수의 결정방법으로 사용되는 최소자승법 (Least Squares Method, LSM)의 단점을 해결하기 위해 해석적으로 계산된 자료를 함께 적용하는 방법과 원자로의 출력분포 측정을 위한 SAM (Shape Annealing Matrix) 결정에 적용한 결과를 기술하고 있다. 해석적 자료를 함께 적용할 경우 연료 연소에 따른 원자로 특성변화를 적절히 반영하여 LSM 추정치의 정확도를 크게 개선할 수 있음을 확인하였다.