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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 15, Issue 4 - Dec 1983
Volume 15, Issue 3 - Sep 1983
Volume 15, Issue 2 - Jun 1983
Volume 15, Issue 1 - Mar 1983
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Two Dimensional Analysis for Equilibrium Core of CANDU-PHWR
Keung Koo Kim ; Seong Yun Kim ; Chang Hyun Chung ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 87~97
The WBURN (2-D, 2-group, coarse mesh) code is developed to analyze the equilibrium core characteristics of CANDU-PHWR. The equilibrium characteristics of Wolsung reactor computed by using WBURN are compared with the values given in the Wolsung FSR. The changes of equilibrium core characteristics caused by the variation of design parameters for operating conditions are also investigated. The numerical results indicate that the average discharge irradiation in the Wolsung reactor can be increased up to about 5%.
Study on the Numerical Analysis of Nuclear Reactor Kinetics Equations
Jae Choon Yang ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 98~109
A two-step alternating direction explicit method is developed to solve the space-dependent reactor kinetics equations in two space dimensions. As a special case in the general class of alternating direction implicit methods, this method is analysed for accuracy and stability. To test the validity of this method it is compared with the implicit-difference method used in the TWIGL program. It is shown that the two methods are closely related. The time dependent neutron fluxes of the pressurized water reactor (PWR), during control rod insertion, and, of the CANDU-PHW reactor, in case of postulated loss of coolant accident, are obtained from the numerical calculation results.
The Uptake and Translocation of Strontium-90 in Soybean Plants
Koon-Ja Lee ; Jeong-Ho Lee ; Su-Rae Lee ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 110~116
The absorption and translocation of strontium-90 by soybean plant, Glycine max, was studied by applying strontium-90 solution on the foliage or on the soil surface right after the first flowering time under greenhouse conditions. The results are summarized as follows. In the foliar application of strontium-90, only a small portion of the radioactivity was translocated to other parts of the plant and most of it remained in the applied leaves, which should cause soil contamination after falling. In the soil surface application of strontium-90, much of the radioactivity was absorbed through the root and translocated to stems and leaves by different patterns depending on the growth stage.
The Solvent Extraction of Uranium(VI) and Other Metal Ions with Pyrazolone Chelating Agents -The Studios on the Rad-Waste Treatment(1)-
Hun Hwee Park ; Nak June Sung ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 117~122
The chelating agent with
-diketo funtional group, 1-phenyl-3-methyl-4-acyl-pyrazolone-5-one, has been used in separating and extracting radionuclides in a waste solution. The derivatives of this pyrazolone compound, prepared by different acyl groups, were synthesized and examined to figure out the extracting ability for Uranium (VI) and Zirconium (IV). The product prepared with succinic anhydride, called succinyl pyrazolone, showed excellent extraction for uranium (VI) in a chloroform solvent system. This result indicates that acyl pyrazolones having carboxylic acid group as a functional group forming
-diketo functionality are very selective for uranium (VI) and generally other metal ions with high valency.
Mechanisms, Experimental Results, Empirical Correlations and Analytic Models of Beat Transfer in Containment Building Following a LOCA
Jong Ho Choi ; Soon Heung Chang ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 123~134
Estimates of the rate of heat removal from the containment atmosphere following a loss of colant accident (LOCA) are important to the prediction of containment peak pressure and temperature which are essential parameters in designing the containment building. An overall survey and discussion of mechanisms, experimental results, empirical correlations and analytical models that are relevant to the heat transfer inside the containment have been made. As a result of this review, the current state of the knowledge about tile containment heat transfer can be understood and it is known that more investigations are needed to avoid the misuse of various correlations.
A modified Borresen's Coarse-Mesh Solution to the LRA-BWR Benchmark Problem
Chang Hyo Kim ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 135~141
Computational accuracy of the modified Borresen's coarse-mesh diffusion theory scheme is investigated with the steady-state solutions of the two- and three-dimensional LRA-BWR bench-mark problem. By comparing the numerical results available for the critical eigenvalue and power distribution of the LRA-BWR, it is shown that the modified scheme is capable of predicting the power distribution of the multi-dimensional BWR problem with an improved accuracy.
Ion Exchange Separation and Spectrofluorometric Determination of Lanthanides in Nuclear Grade Material
Ki-Soo Cho ; In-Suck Suh ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 142~148
Distribution coefficients between cation exchange resin (Dowex 50W
-hydroxyisobutric acid (
-HIBA) are measured in order to separate traces of Sm, Eu, Gd and Dy from nuclear material. Individual separations are performed by pH gradient technique with 0.40M
-HIBA from 3.40 to 3.60 in cation exchange resin after a group separation. Each of separated elements is determined with a fluorometric method except Gd by colorimetry. The results are applied to analyze Sm, Eu, Gd and Dy in magnesium diuranate (yellow cake).
Adsorptive Bubble Separation of Zinc (II) Using Capric Acid as Collector
Chung Hee Kwak ; Chul Lee ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 149~153
The removal of zinc (II) from aqueous solutions has been studied by the adsorptive bubble separation processes such as solvent sublation and foam fractionation processes using capric acid as collector. The efficiency of the remoal process has been studied by changing the ionic strength and pH and the bubble separation method has been compared with the solvent extraction process using the capric acid dissolved in benzene as extractant.
The Canadian Nuclear Regulatory Philosophy
Jennekens, J.H. ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 154~159
The principles and practices of national nuclear regulatory agencies around the world differ significantly. This paper outlines the philosophical approach to nuclear regulation of the Atomic Energy Control Board of Canada and attempts to explain the principles which have governed the Board's licensing and compliance programs during the past 37 years.
The Neutron Prospects After the Golden Anniversary of Its Discovery
Whittemore, W.L. ;
Nuclear Engineering and Technology, volume 15, issue 2, 1983, Pages 160~168
About 25 years ago, halfway along the recorded history of the neutron as a separate entity, Korea entered the nuclear age and initiated its own neutron research and development programs. Since that time Korean scientists have taken all possible advantages of the special opportunities offered by the neutron. Scientists the world over, in the Far East, hear East, and the West, have adapted these opportunities to their special needs. These needs are manifested in all phases of modern life, including power generation by nuclear means, food preservation, production of new types of food-bearing plants, commercial uses of activation analysis, irradiations, and isotope production, nuclear medicine, industrial quality control through nuclear measurements, and direct use of neutrons in research in many areas including solid state physics, chemistry, physics, biology, and medicine. Research with neutrons has been successfully conducted using nuclear research reactors of all sizes ranging from the very small (∼10 kilowatts) to the very large(50-100 Megawatts). This speaker has teen associated with nuclear research since 1945 and directly with neutron research since 1957. From this continuous research and development activity, he will report on some of the prospects in the second 50 years of the neutron.