• Proceedings of the Korea Society for Simulation Conference
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• 2005.11a
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• pp.153-158
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• 2005

영광 원자력발전소 1호기가 16주기로 운전됨에 따라 훈련용 시뮬레이터의 입력자료 또한 16주기가 반영되어야 한다. 시뮬레이터의 여러 모델 중 노심모델(REMARK)에 필요한 입력자료는 Westinghouse의 핵 설계 코드체계인 APA 시스템의 Output에서 얻을 수 있으나 그 양이 방대하기 때문에 수작업을 통한 입력자료 생산은 큰 어려움을 갖는다. 따라서 이러한 작업을 수행할 프로그램 개발이 필수적이며 개발된 프로그램을 매 교체주기마다 적용하여 노심모델에 대한 원활한 입력상수 생산을 가능하게 할 수 있다.

• Proceedings of the Korea Society for Simulation Conference
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• 2005.11a
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• pp.165-170
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• 2005

원전 시뮬레이터의 노심모델(REMARK)은 원자로에서 발생하는 1차원 열원을 정확히 모사하고, 정상상태 및 과도상태의 반응도 변화에 따른 중성자속의 거동을 실제 원자로와 유사하게 모사할 수 있어야 한다. 모사의 정확성을 높이기 위해 Tuning 작업이 필수적이나 그 작업 단계가 매우 복잡하여 많은 시간과 노력이 필요하기 때문에 이를 간소화하면서 정확성을 높일 수 있는 Tuning 지원 프로그램을 개발하였다. 개발된 프로그램의 사용결과 신속하고 정확한 Tuning이 가능하였다.

• Nuclear Engineering and Technology
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• v.48 no.1
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• pp.129-143
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• 2016

Sometimes, we need or try to figure out somebody's thoughts from his or her behaviors such as eye movement, facial expression, gestures, and motions. In safety-critical and complex systems such as nuclear power plants, the inference of operators' thoughts (understanding or diagnosis of a current situation) might provide a lot of opportunities for useful applications, such as development of an improved operator training program, a new type of operator support system, and human performance measures for human factor validation. In this experimental study, a novel method for inference of an operator's thoughts from his or her eye movement data is proposed and evaluated with a nuclear power plant simulator. In the experiments, about 80% of operators' thoughts can be inferred correctly using the proposed method.

• Nuclear Engineering and Technology
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• v.37 no.1
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• pp.118-126
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• 2005

While emergency operating procedures (EOPs) occupy an important role in the management of various abnormal situations in nuclear power plants (NPPs), current technology for the validation of EOPs still largely depends on manual review. A validation method for EOPs of NPPs is thus proposed based on dynamic multi-level flow modeling (MFM). The MFM modeling procedure and the EOP validation procedure are developed and provided in the paper. Application of the proposed method to EOPs of an actual NPP shows that the proposed method provides an efficient means of validating EOPs. It is also found that the information on state transitions in MFM models during the management of abnormal situations is also useful for further analysis on EOPs including their optimization.

• Nuclear Engineering and Technology
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• v.54 no.8
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• pp.2783-2791
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• 2022

Molecular dynamics simulations were performed to predict the behavior of graphite atoms under neutron irradiation using large-scale atomic/molecular massively parallel simulator (LAMMPS) package with adaptive intermolecular reactive empirical bond order (AIREBOM) potential. Defect structures of graphite were compared with results from previous studies by means of density functional theory (DFT) calculations. The quantitative relation between primary knock-on atom (PKA) energy and irradiation damage on graphite was calculated. and the effect of PKA direction on the amount of defects is estimated by counting displaced atoms. Defects are classified into four groups: structural defects, energy defects, vacancies, and near-defect structures, where a structural defect is further subdivided into six types by decision tree method which is one of the supervised machine learning techniques.

• Journal of the Korea Society for Simulation
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• v.3 no.1
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• pp.135-150
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• 1994

일반 산업체와 화력발전소 계측제어시스템에 널리 사용되고 있는 분산제어시스템(Distributed Control System)을 원자력발전소에 사용하기 위해서는 분산제어시스템의 안전성과 신뢰성의 입증이 선결과제이다. 따라서 새로운 시스템을 시뮬레이션에 의해 구현하고 검증하기 위한 시뮬레이터가 필요하게 되었다. 발전소 전범위 시뮬레이터(full Scope Simulator)를 제작 하기에 앞서 발전소 계통 중에서 소규모계통을 대상으로 부분범위 시뮬레이터(Compact Simulator)를 제작하였다. 개발된 DCS 검증용 시뮬레이터의 시스템은 발전소 제어반을 모의한 소프트 패널, 발전소 프로세스을 모이한 계통 모델링 소프트웨어, 그리고 현재 발전소의 아날로그 제어계통을 대신한 DCS 제어 계통등의 세 개의 계통으로 구성하였다. 개발 제작된 시뮬레이터를 이용하여 원자력 발전소 계측제어시스템에 분산제어시스템 적용을 시뮬레이션을 통햐여 구현하였으며 분산제어시스템의 적용 검증작업은 물론 적용을 위한 설계업부에도 DCS 검증용 시뮬레이터가 효과적으로 사용될 수 있음을 알았다.

• Proceedings of the KIEE Conference
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• 2002.07a
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• pp.265-267
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• 2002

This paper deals with an I/O simulator design for performance evaluation of reactor protection systems in nuclear power plants. The I/O simulator provides input signals for the reactor protection system, and acquires output signals from the initiation circuits. The simulator is based on VMEbus system, and all VMEbus boards are developed within the country.

• KEPCO Journal on Electric Power and Energy
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• v.5 no.3
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• pp.165-171
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• 2019

The steam turbine used in nuclear power plant is modeled for the purpose of verification of control system rather than the operator education. The valves, reheater and generator are modeled also and integrated into the simulator. After that, the operation data and the designed data such as heat balance diagram are utilized to identify the model parameters. It was evident that model outputs of developed simulator are very close to the measured operating ones. The simulator within dynamic model was used to verify and validate the whole control system together with field instruments. And the target plant has been operating long time.

• Fire Science and Engineering
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• v.27 no.2
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• pp.80-88
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• 2013

The validation of Fire Dynamics Simulator (FDS) was conducted for the under-ventilated fire in well-confined multi-compartments representative of nuclear power plant. Numerical results were compared with experimental data obtained by the OECD/NEA PRISME project. The effects of the numerical boundary conditions (B.C.) in ventilated system and the flame suppression model applied within FDS on the thermal and chemical environments inside the compartment were discussed in details. It was found that numerical B.C. on the vent flow resulting from over-pressure at ignition and under-pressure at extinction should be considered carefully in order to predict accurately the species concentrations rather than temperatures and heat fluxes inside the multi-compartment. The default information of suppression model applied within FDS resulted in artificial phenomena such as flame extinction and re-ignition, and thus the FDS results on the under-ventilated fire showed good agreement with the experimental results as the modified suppression criteria of the fuel used was adopted.

• Journal of the Korean Society of Safety
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• v.31 no.2
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• pp.1-9
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• 2016

The standard procedure of fire modeling was reviewed to minimize the user dependence, based on the NUREG-1934 and 1824 reports. The hazard analysis of lubricating oil fires in the air compressor room of domestic nuclear power plant (NPP) was also performed using a representative fire model, FDS (Fire Dynamics Simulator). The area ($A_f$) and location of fire source were considered as major parameters for the realistic fire scenarios. As a result, the maximum probability to exceed the thermal damage criteria of IEEE-383 unqualified electrical cables was predicted as approximately 70% with $A_f=1m^2$. It was also found that for qualified electrical cables, the maximum probabilities of exceeding the criteria were 2% and 90% with $A_f=2$ and $4m^2$, respectively. It was concluded that all electrical cables should be replaced with IEEE-383 qualified cables and the dike to restrict as $A_f{\leq}2m^2$ should be installed at the same time, in order to assure the thermal stability of electrical cables for lubricating oil fires in the air compressor room of domestic NPP.