• Journal of Radiation Protection and Research
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• 제28권3호
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• pp.239-245
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• 2003

Every nuclear power plant measured concentrations of tritium in groundwater and surface water around the plants periodically. It was not easy to predict the tritium concentration only with these measurement data in case of various release scenarios. KAERI developed a new approach to find the relationship between the tritium release rate and tritium concentration in the environment. The approach was based upon a dynamic compartment model. In this paper the dynamic compartment model was modified to predict the tritium behavior more accurately. The mechanisms considered for the transfer of tritium between the compartments were evaporation, groundwater flow, infiltration, runoff, and hydrodynamic dispersion. Time dependent source terms of the compartment model were introduced to refine the release scenarios. Also, transfer coefficients between the compartments were obtained using realistic geographical data. In order to illustrate the model various release scenarios were developed, and the change of tritium concentration in groundwater and surface water around the nuclear power plants was estimated.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.117-122
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• 1995

An Integrated Test Facility(ITF) is a human factors experimental environment to evaluate an advanced man machine interface(MMI) design. The ITF includes a human machine simulator(HMS) comprised of a nuclear power plant function simulator, man-machine interface, experiment control station for the experiment control and design, human behavioural data measurement system, and data analysis and experiment evaluation supporting system(DAEXESS). The most important features of ITF is to secure the flexibility and expandibility of Man Machine Interlace(MMI) design to change easily the environment of experiments to accomplish the experiment's objects In this paper, we describe a development scope and characteristics of the ITF such as, hardware and software development scope and characteristics, system thermohydraulic modelling characteristics, and experiment station characteristics for the experiment variables design and control, to be used as an experiment environment for the evaluation of VDU-based control room.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2006년도 심포지엄 논문집 정보 및 제어부문
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• pp.138-140
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• 2006

A new diagnosis model was constructed by combining atomic force microscopy (AFM), wavelet, and neural network. Plasma faults were characterized by filtering AFM-measured etch surface roughness with wavelet. The presented technique was evaluated with the data collected during the etching of silicon oxynitride thin film. A total of 17 etch experiments were conducted. Applying wavelet to AFM, surface roughness was detailed into vertical, horizon%at, and diagonal components. For each component, neural network recognition models were constructed and evaluated. Comparisons revealed that the vertical component-based model yielded about 30% improvement in the recognition accuracy over others. The presented technique was evaluated with the data collected during the etching of silicon oxynitride thin film. A total of 17 etch experiments were conducted

• Nuclear Engineering and Technology
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• 제12권3호
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• pp.180-193
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• 1980

경수의 엔탈피, 비체적(比體積), 점성, 열전도도 및 임계엔트로피등은 경수로의 핵특성 분석에 필수적인 자료이다. 본 보고서에서는 상기 자료를 신속, 정확하게 구할 수 있는 부(副)프로그램을 개발하여 경수로의 핵계산코드에서 보편적으로 사용할 수 있게 하였다. 기본자료로 ASME Steam Tables (1967)과 이의 개정판 (1975)을 사용하였다. 경수로의 핵계산에서 사용되는 온도 및 압력의 영역에서 이 프로그램의 계산치는 기준치와 오차 0.2%내에 들어 있음이 입증되었다.

• Nuclear Engineering and Technology
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• 제24권1호
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• pp.1-13
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• 1992

ORIGEN2 전산코드를 위한 연구로용 1군 단면적 데이타베이스를 개발하였다. 여기에는 EN-DF/B-lV와 -V가 기 본 핵 자료로 사용되었고 이들은 NJOY 코드시스템을 사용하여 69군으로 처리되었다. 1군 축약을 위한 가중함수는 핵연료의 연소에 따른 KMRR의 중성자 스펙트럼을 WIMS-KAERI코드로 계산하여 사용하였다. 새로 개발된 데이타베이스는 KMRR핵연료의 연소에 따른 악티나이드 생성량 평가를 통해 상세 다군 수송계산 결과와 잘 일치함이 입증되었다. 그리고 새로운 데이타베이스를 이용하여 KMRR의 사용후 핵연료 특성을 분석하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.363-364
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.61.1-61.1
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• 2003

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.143.1-143.1
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• 2003

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.73-73
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• 1998

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.1319-1320
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• 2005