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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Nuclear Engineering and Technology
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Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 30, Issue 6 - Dec 1998
Volume 30, Issue 5 - Oct 1998
Volume 30, Issue 4 - Aug 1998
Volume 30, Issue 3 - Jun 1998
Volume 30, Issue 2 - Apr 1998
Volume 30, Issue 1 - Feb 1998
Selecting the target year
The Effects of pH and Buffer Materials on the Leaching of Simulated Waste Glass
Kim, S. S. ; Kim, J. G. ; Kim, J. S. ; K. S. Chun ; Lee, G. H. ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 1~7
Effects of pH, bentonite and Portland cement on the leaching of the simulated waste glass were investigated. The simulated waste glass showed the low leach rate in the neutral pH region, while the leach rate in both acidic and alkaline regions increased. Addition of bentonite to the leachant enhanced the leaching of the waste glass. When the waste glass was leached at 72
for 36 days in the ground water with gel state Na-bentonite, approximately 2.2
of the surface was corroded out and the large amount of Ti, Nd, and Zr was observed on the surface. The amount of B leached from the simulated waste glass in the presence of domestic bentonite was about three times higher than that in the presence of Aldrich bentonite as well as Portland cement.
Development of Automatic Reactor Internal Vibration Monitoring System Using Fuzzy Peak Detection and Vibration Mode Decision Method
Kang, Hyun-Gook ; Seong, Poong-Hyun ; Park, Heui-Youn ; Lee, Cheol-Kwon ; Koo, In-Soo ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 8~16
In this work a method to detect the vibrational peak and to decide the vibrational mode of detected peak for core internal vibration monitoring system which is particularly concerned on the core support barrel (CSB) and fuel assemblies is developed. Flow induced vibration and aging process in the reactor internals cause unsoundness of the internal structure. In order to monitor the vibrational status of core internal, signals from the ex-core neutron detectors are transformed into frequency domain. By analyzing transformed frequency domain signal, an analyst can acquire the information on the vibrational characteristics of the structures, i.e., vibration frequencies of each component, vibrational level, modes of vibration, and the causes of the abnormal vibration, if any. This study is focused on the development of the automated monitoring system. Several methods are surveyed to define the peaks in power spectrum and fuzzy theory is used to automatic detection of the vibrational peaks. Fuzzy algorithm is adopted to define the modes of vibration using the peak values from fuzzy peak recognition, phase spectrum, and coherence spectrum.
Numerical Analysis of Impurity Transport Along Magnetic Field Lines in Tokamak Scrape-011 Layer
Chung, Tae-Kyun ; Hong, Sang-Hee ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 17~25
Transport of carbon and boron impurity ions parallel to magnetic field lines in the tokamak SOL (scrape-off layer) is numerically investigated for a one-dimensional steady state. The spatial distributions of density and velocity of the impurity ions in a steady state are calculated by finite difference method for a single-fluid model. The calculated results show that among forces acting on SOL particles thermal force produced tv plasma temperature gradient is a principal force determining the feature of impurity distribution profiles in the tokamak edge. However, strong collisional friction forces appearing dominant in front of the diverter plate restrain impurity ion flows due to temperature gradients from moving toward the midplane. Consequently, the stagnation point develops in the impurity flow by these two forces near the diverter region, in which ion flows change their directions. Impurity ions turn out to be accumulated at the stagnation points, where peaked profiles of highly-ionized state ions are relatively predominant over those of low-ionized state ions
PCCS Analysis Model for the Passively Cooled Steel Containment
Hwang, Y.D. ; Chung, B.D. ; Cho, B.H. ; Chang, M.H. ; Jeong, Ik ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 26~39
The containment pressure and temperature transient analysis computer code CONTEMPT4/MOD5 is modified to incorporate the passive containment cooling models. The correlations are selected from the existing experimental heat transfer correlations to model the natural and mixed convection in annular space between the containment shell and the shield building. The evaporative heat transfer of the water film on the outer shell of the containment is modeled using the correlations derived from the analogy between the heat and mass transfer. The modified code is applied to the Ap600 containment transient analysis for the model verification and the results are compared to the results of GOTHIC calculation done by Westinghouse. Also, d series of parametric sensitivity studies of heat transfer correlations, water film ratio and delay time of the wet cooling on the containment peak pressure and temperature following LOCA are performed for the containment of 1000MWe passive plant, KP1000.
The Characteristics of a Pump at Nearly Saturated State
Kim, S. N. ; Kim, J. C. ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 40~46
A set of experiments using a 1/10 scale model pump which was manufactured to simulate performance of reactor coolant pump(RCP) of Y.G.N # 3 and 4, was executed in single phase(at atmospheric pressure and room temperature) and near-saturation(300 ~ 600kPa). The pump characteristics in single phase flow was similar to the characteristics of the RCP. The pump characteristic curves at nearly saturated state were correlated in terms of flow coefficient and head coefficient for subcooled temperature using the cavitation number defined as (equation omitted), which can be predicted the cavitation possibility. The pump behavior around the saturated temperature almost consists with single phase behavior until the cavitation occurs(When cavitation occurs. When the flow coefficient is about 0.12), the pump head rapidly degrades. In this situation, subcooled temperature is about 1.8~8
and cavitation number of model pump is 1.0 ~ 1.7.
Establishment of the Procedure to Prevent Boron Precipitation During Post-LOCA Long Term Cooling for WH 3-Loop NPPs
H. R. Cho ; Lee, S. K. ; C. H. Ban ; S. T. Hwang ; B. H. Chang ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 47~57
Boric acid concentrations of the refueling water storage tank and the accumulators for Westinghouse 3-loop type plants are increased to meet the post loss of coolant accident shutdown requirement for the extended fuel cycles from 12 months to 18 months. To maintain long term cooling capability following a LOCA, the switchover time is examined using BORON code to prevent the boron precipitation in the reactor core with the increased boron concentrations. The analysis results show that hot leg recirculation switchover times are shortened to 7.5 hours from 24 hours after the initiation of LOCA for Kori 3&4 and 8 hours from 18 hours for Ulchin 1&2, respectively. The How path in the mode J for Kori 3&4 is recommended to realign to the simultaneous recirculation of both hot and cold legs from the cold leg recirculation, as done by Ulchin 1&2.
Development of a Computer Code, CONPAS, for an Integrated Level 2 PSA
Ahn, Kwang-Il ; Kim, See-Darl ; Song, Yong-Mann ; Jin, Young-Ho ; Park, Chung K. ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 58~74
A PC window-based computer code, CONPAS (CONtainment Performance Analysis System), has been developed to integrate the numerical, graphical, and results-operation aspects of Level 2 probabilistic safety assessments (PSA) for nuclear power plants automatically. As a main logic for accident progression analysis, it employs a concept of the small containment phenomenological event tree (CPET) helpful to trace out visually individual accident progressions and of the detailed supporting event tree (DSET) for its detailed quantification. For the integrated analysis of Level 2 PSA, the code utilizes five distinct, but closely related modules. Its computational feasibility to real PSAs has been assessed through an application to the UCN 3&4 full scope Level 2 PSA. Compared with other existing computer codes for Level 2 PSA, the CONPAS code provides several advanced features: (1) systematic uncertainty analysis / importance analysis / sensitivity analysis, (2) table / graphical display & print, (3) employment of the recent Level 2 PSA technologies, and (4) highly effective user interface. The main purpose of this paper is to introduce the key features of CONPAS code and results of its feasibility study.
Food Irradiarion : An Alternative Technology for an Emerging Need
Yang, Jae-Seung ;
Nuclear Engineering and Technology, volume 30, issue 1, 1998, Pages 75~82
Development and implementation of food irradiation was driven by needs pertaining to food safety improvement, food spoilage reduction, and quarantine/trade. The need for food safety is caused by the increasing morbidity and mortality caused by food-borne diseases worldwide, and it affects national economy and world-trade. Radiation technology can serve to ameliorate the vulnerability of our food supply system.