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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 15, Issue 4 - Dec 1983
Volume 15, Issue 3 - Sep 1983
Volume 15, Issue 2 - Jun 1983
Volume 15, Issue 1 - Mar 1983
Selecting the target year
Preparation of Permselective Membrane by Mean of a Radiation-Induced Grafting
Young Kun Kong ; Hoon Seun Chang ; Chong Kwang Lee ; Jae Ho Choi ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 1~10
By controlling both the means of grafting and the cast-solution components, no degradation and dimensional change of radiation-induced graft polymerization were found. The electric resistance of styrene-cellulose acetate grafts increases with increasing styrene content, while those for the hydrophilic monomers show no marked effect. In comparison with the grafted cellulose acetate membrane by simultaneous irradiation method, the appearance of the grafted membrane by post-polymerization method was not markedly changed irrespective of the percent of grafting and radiation dose of electron beam or
-ray. The combination of crosslinking agents such as divinyl benzene (OB) or trimethyl propane triacrylate (TMPT) in the VP:St:BPO system leads to gradual increase of the percent of grafting. The activation energy for grafting of St:VP:BPO solution onto cellulose acetate membrane was determined to be about 21.8 Kcal/mole over the range of 55
. The initial rate of grafting (in %/hr) is proportional to the power 0.76 for dose intensities.
A Reliability Analysis of CVCS
Chung Chan Lee ; Byung Soo Lee ; Chang Sun Kang ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 11~22
The reliability of the Chemical and Volume Control System has been analyzed in a pressurized water reactor. The boration failure was taken to be the top event for this reliability analysis. A detailed fault tree was constructed and the minimal cut sets were derived. It was computed that the unavailability of the Chemical and Volume Control System due to boration failure was 1.497
during plant operation. It was found that the reliability of boric acid transfer pumps were the most important factors in the availability of the Chemical and Volume Control System. As expected, human errors also introduce the high system unavilability.
Geochronological Study on Gyeonggi Massif in Korea Peninsula by the Rb-Sr Method
Seung Hwan Choo ; Dong Hak Kim ; Won Mok Jae ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 23~32
In the previous studies on Rb-Sr geochronology, Gyeonggi Massif was known as the oldest rock in Korea Peninsula but the detailed sequence of geochronology was not studied yet. In the present study, some of whole rock isochrons considered here can be geochronologically grouped as follows: The ages of leucocratic gneisses at Yangpyeong, and augen and banded gneisses at Anyang show 2200 to 2300 m.y. which may represent the time of the Massif formation or an igneous intrusion. The age of the granite gneiss distributed in Yangpyeong area shows about 1400 m.y., which apparently represents the intrusion time of the gneiss. The age of the extremely altered metamorphic rock shows about 500 m.y., which may represent the time of a Caledonian orogenic event probably with hydrothermal activities. The other episodic ages of 800 to 900 m.y. which was widely observed through the Massif, may represent the ages of Precambrian igneous activities or regional metamorphism in the Massif. It seems to be reasonable that the ages of 120 to 270 m.y. show the times of Mesozoic and Late Palaeozoic Plutonisms in the Massif.
A Study of Iteration Method for 2-Dimensional 2-Group Diffusion Problems
Jong Hwa Chang ; Kil Yoo Kim ; Chang Hyun Chung ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 33~40
It is shown that the Shanks sequence
-transformation and the conventional extrapolation method are theoretically related. The
-transformation method is then applied for the multigroup diffusion problems. The diffusion code, CITATION, is modified for this study and the computing time is compared for each iteration tactics. The Equipose method, in which only sing1e inner iteration for each energy group is carried for an outer iteration, has been known as the fastest iteration method. However, in the case of 3-group problems, the proposed method, in which the number of inner iteration for the fast and thermal group is 2 and 1 respectively, gives better convergency than the Equipose method by about 12%. The double extrapolation method results in faster computing time than the single extrapolation method without computing storage problem. It is, however, to note that this method is verified only for a two-group treatment.t.
A Computer Code Development for Updating Reliability Data Using Bayes' Theorem and Its Application
Won-Guk Hwang ; Kun Joong Yoo ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 41~49
A computer code, BERD (Bayesian Estimation of Reliability Data), has been developed and tested in order to update the data for the reliability analysis of safety related systems in a specific nuclear power plant. The code has been used to derive the plant-specific data for reliability analysis of the auxiliary feedwater system of a pressurized water reactor. The prior information for components selected was taken from the U.S. Reactor Safety Study, WASH-1400, and the operating experiences from published licensee event reports. The results show that the updated data are well fitted to log-normal distribution curves and the error factors are reduced significantly.
Buoyancy Effects on Turbulent Mixing in the LMFBR Outlet Plenum
Soon Heung Chang ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 50~56
The effect of flow stratification is of particular concern during transient after scram in the outlet plenum of LMFBR. In this case, buoyancy effects on turbulent mixing are of importance to designers. An investigation has been made to identify the appropriate change in the available turbulence models which are necessary to include the effects of buoyancy on turbulence transport equations. The developed physical model of the buoyant turbulent flow are solved through SMAC method. Testing of the developed numerical model was undertaken and compared with experimental results. The results show that the buoyant turbulent effects account for a significant increase in the stability of the stratification, with a strong suppression of turbulence in the outlet plenum.
Review of Calculational Model for the Performance of CANDU-Type Nuclear Development and Parametric Study on the Fuel Performance
Man Sung Yim ; Un Chul Lee ; Ho Chun Suk ;
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 57~69
The LWR fuel performance analysis computer code, FRAPCON-1, are evaluated to investigate the performance of CANDU fuel elements loaded in Wolsung-1 reactor. The FRAPCON-1 models of neutron flux depression in fuel and of fuel-to-cladding heat transfer are modified, and the validity of fission gas release model for CANDU fuel is evaluated. And the heavy water properties are provided in calculating the heat transfer coefficient between cladding and coolant. By using the modified code, FRAPCON-1-CSK, the sensitivity studies are carried out for Wolsung-1 fuel element design parameters. The performance analysis is also performed for Wolsung-l fuel elements. The calculated results are discussed in terms of. LWR fuel design criteria because of unavailability of CANDU fuel design criteria.
월성원자로의 초임계 및 노물시험식
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 70~78
Nuclear Engineering and Technology, volume 15, issue 1, 1983, Pages 79~86