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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 29, Issue 6 - Dec 1997
Volume 29, Issue 5 - Oct 1997
Volume 29, Issue 4 - Aug 1997
Volume 29, Issue 3 - Jun 1997
Volume 29, Issue 2 - Apr 1997
Volume 29, Issue 1 - Feb 1997
Selecting the target year
추적자 방법에 의한 유량측정법
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 1~7
영광 3호기 1주기 시운전 자료를 통한 ONED94 코드의 검증
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 8~16
콘크리트를 통한 핵종의 확산계수
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 17~28
고리 1호기 ASME 펌프 가동중 시험주기 요건완화
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 29~41
증기발생기 스너버 링크장치 계통의 기하학적 해석
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 42~48
임계 열유속(CHF) 상관식 형태와 적용 방법에 따른 예측 오차 및 여유도
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 49~59
용융염 전해방법에 의한 핵연료 Sludge처리
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 60~64
A Dependability Modeling of Software Under Memory Faults for Digital System in Nuclear Power Plants
Park, Jong-Gyun ; Seong, Poong-Hyun ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 433~443
In this work, an analytic approach to the dependability of software in the operational phase is suggested with special attention to the hardware fault effects on the software behavior : The hardware faults considered are memory faults and the dependability measure in question is the reliability. The model is based on the simple reliability theory and the graph theory which represents the software with graph composed of nodes and arcs. Through proper transformation, the graph can be reduced to a simple two-node graph and the software reliability is derived from this graph. Using this model, we predict the reliability of an application software in the digital system (ILS) in the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. We also found that the effects of the hardware faults on the software failure should be considered for predicting the software dependability accurately in operation phase, especially for the software which is executed frequently. This modeling method is particularly attractive for the medium size programs such as the microprocessor-based nuclear safety logic program.
Reliability Assessments and Design Load Factors for Reinforced Concrete Containment Structures of Nuclear Power Plant
Han, Bong-Koo ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 444~450
The current ASME code for reinforced concrete containment structures are not based on probability concepts. The stochastic nature of natural hazard or accidental loads and the variations of material properties require a probabilistic approach for a rational assessment of structural safety and performance. The paper develops design load factors for the serviceability limit state of reinforced concrete containment structures. The target limit state probability is determined and the load factors are calculated by the numerical analysis. Design load factors are proposed and carried out the reliability assessments.
Signal Shapes from a Closed-ended Coaxial HPGe Detector
Park, H. D. ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 451~458
Signal shapes from a closed-ended coaxial HPGe detector are investigated by numerical methods. The detector used in this study has a volume of 72 ㎤ with relative efficiency of 15%. The electric field and potential distributions in the detector are determined by solving the Poisson equation at the depletion and operating bias. Hence the time dependent signal shapes induced on the electrode are obtained from the energy balance consideration and tv solving the equation of motion for the charge carriers. For various initial positions of a charge carrier pair, the collection times of induced charge vary in the range of 70 - 404 nsec.
Monte Carlo Simulation for Particle Behavior of Recycling Neutrals in a Tokamak Diverter Region
Kim, Deok-Kyu ; Hong, Sang-Hee ; Kihak Im ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 459~467
The steady-state behavior of recycling neutral atoms in a tokamak edge region has been analyzed through a two-dimensional Monte Carlo simulation. A particle tracking algorithm used in earlier research on the neutral particle transport is applied to this Monte Carlo simulation in order to perform more accurate calculations with the EDGETRAN code which was previously developed for a two-dimensional edge plasma transport in the authors' laboratory. The physical model of neutral recycling includes charge-exchange and ionization interactions between plasmas and neutral atoms. The reflection processes of incident particles on the device wall are described by empirical formulas. Calculations for density, energy, and velocity distributions of neutral deuterium-tritium atoms have been carried out for a medium-sized tokamak with a double-null configuration based on the KT-2 conceptual design. The input plasma parameters such as plasma density, ion and electron temperatures, and ion fluid velocity are provided from the EDGETRAN calculations. As a result of the present numerical analysis, it is noticed that a significant drop of the neutral atom density appears in the region of high plasma density and that the similar distribution of neutral energy to that of plasma ions is present as frequently reported in other studies. Relations between edge plasma conditions and the neutral recycling behavior are discussed from the numerical results obtained herein.
Transient Photocurrent in Amorphous Silicon Radiation Detectors
Lee, Hyoung-Koo ; Suh, Tae-Suk ; Choe, Bo-Young ; Shinn, Kyung-Sub ; Cho, Gyu-Seong ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 468~475
The transient photocurrent in amorphous silicon radiation detectors (n-i-n and forward biased p-i-n) were analyzed. The transient photocurrents in these devices could be modeled using multiple trap levels in the forbidden gap. Using this model the rise and decay shapes of the photocurrents could be fitted. The decaying photocurrent shapes of the p-i-n and n-i-n devices after a short duration of light pulse showed a similar behavior at low dark current density levels, but at higher dark current density levels the photocurrent of the p-i-n diode decayed faster than that of the n-i-n, which could be explained by the decreased electron lifetimes in the forward biased p-i-n diode at high dark current densities. The transient photoconductive gain behaviors in the amorphous silicon radiation detectors are discussed in terms of device configuration, dark current density and time scale.
Stress Analysis of Top Hat Type Structure for Random Loading
M. J. Jhung ; Kim, Y. B. ; Lee, J. B. ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 476~487
To resolve several arguments raised for the current analysis of a structure like top hat, which is composed of flange, cylinder and plate, the dynamic response analysis is performed for the full and half models. The dynamic characteristics are investigated for full and half models and the results are compared between them. The responses such as bolt reactions and stresses due to random loading are also obtained using the analysis capabilities between commercial programs which have the routine for the random vibration analysis. Several general purpose structural analysis programs are used to get the response due to the random loadings. Also the application of the random loading and the effect of correlations such as fully correlated, partially correlated and fully uncorrelated cases are studied and the general directions for the generation of design loads due to random loading are suggested.
Measurement of the Moderator Temperature Coefficient of Reactivity for Pressurized Water Reactors
Yu, Sung-Sik ; Kim, Se-Chang ; Na, Young-Whan ; Kim, H. S. ; J. Y. Doo ; Kim, D. K. ; S. W. Long ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 488~499
The measurements of the moderator temperature coefficient (MTC) are performed to demonstrate that the calculational model produces results that are consistent with the measurements. Since negative MTC is also a technical specification value that may limit the cycle length, it is important to measure it as accurately as possible. In this report, preferred choice of test method depending on the time in cycle, best power indication and temperature definition in MTC calculation were determined based on the MTC test results taken during initial startup testing and at 2/3 cycle burnup in the Yonggwang nuclear power plant. The results show that the ratio and rodded methods provided good agreement with the predictions during initial startup testing. However, near end-of-cycle the depletion method gives better results, and so is suggested to be used in the MTC measurements at 2/3 cycle burnup. The use of primary Delta T power as a power indicator in the MTC calculations is highly advisable since it responds with good consistent results very quickly to changes unlike secondary calorimetric power. For the appropriate temperature definitions used in the MTC calculations, it is considered that the arithmetic average temperature measured simply by inlet and outlet thermocouples is preferred. Although volumetric average temperature provides better results, the improvement is not sufficient to compensate for the simplicity of calculations by arithmetic average temperature.
General Survey of Detection Methods for Irradiated Foods
Yang, Jae-Seung ;
Nuclear Engineering and Technology, volume 29, issue 6, 1997, Pages 500~507
The development of detection techniques is needed, in order for regulating authorities to determine whether or not a particular food sample has been irradiated, and label it accordingly so that a consumer's free choice can be exercised. The chemical and physical changes brought about in foods by practical doses of irradiation are very small, and therefore very sensitive methods are required. A number of promising approaches have been developed and evaluated. These include chemical, physical and biological methods ranging from the very simple to highly sophisticated techniques.