Go to the main menu
Skip to content
Go to bottom
REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
Editor in Chief :
Volume & Issues
Volume 13, Issue 4 - Dec 1981
Volume 13, Issue 3 - Sep 1981
Volume 13, Issue 2 - Jun 1981
Volume 13, Issue 1 - Mar 1981
Selecting the target year
Model Calculation of the Np-237 Fission Cross-Sections for En=0 to 20 MeV
H.I. Bak ; B. Strohmaier ; M.Uhl ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 207~220
The Np-237 fission cross-sections up to 20 MeV incident neutron energy are calculated by means of the computer code STAPRE- a statistical model code with consideration of preequilibrium decay. The higher chance fissions up to third compound nucleus are taken into account, and the main input parameters in the treatment of fission under consideration of a double-humped fission barrier are carefully adjusted, so that the current trend of experimental data can be fitted within an apparent deviation of about 10% throughout the entire energy range. Results are presented in the form of point-wise cross-section values, and also in the form of graph to demonstrate the shape agreement.
--BHC Residues in Rice Grain
Su-Rae Lee ; Yong-Hwa Kim ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 221~228
C)-BHC was applied to rice plants grown in a pot and its fate in the growth, polishing and oil-extraction processes of the grain was investigated. The
C-activity was absorbed and translocated widely in the plant and the recovery of applied
C-activity in the straw and grain was about 2.8%, of which 9.4% was found in the brown rice. The % partitioning of
C-residues in bran and polished rice was 12:88 and that in oil and oilcake was 37 : 63. Characterization of
C-residues indicated the presence of
-BHC, pentachlorocyclohexene, trichlorobenzene and hydrophilic metabolites, whose proportions were different in the straw and grain.
A Study of Boron Determination in High Purity Aluminum by Capture Gamma-Ray Measurement
Nak Bae Kim ; Hae-Ill Bak ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 229~236
The boron content in reactor grade aluminum has been determined by means of a capture gamma-ray counting method. The experimental detection limit is found to be 5.7% ppm with 10% uncertainty. In order to improve the sensitivity, the boron is preconcentrated from aluminum by cation exchange resin system. The accuracies of both methods, i.e., one by the direct measurement and the other by the measurement after preconcentration, are checked by an additive method. The results show good agreements with less than 5% deviation.
Determination of Impurities in Uranium Dioxide by Neutron Activation Analysis
Nak Bae Kim ; Hae-Ill Bak ; Chul Lee ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 237~244
The preliminary concentration of trace elements in uranium dioxide using an anion exchange resin is presented for neutron activation analysis. The uranyl solution in sulfuric acid is adjusted to the acidity of about pH 2.7 and loaded on a column of the anion exchange resin. An appropriate volume of eluates obtained from the column shows good recoveries of trace elements. By combining this preconcentration with a radiochemical separation scheme, which was developed for the determinations of impurities in aluminum, it is possible to determine 21 trace elements in reactor grade uranium dioxide.
Applications of Irradiation to Polyethylene for Flame Retarded Wire and Cable Insulation
Young Kun Kong ; Hoon Seun Chang ; Chong Kwang Lee ; Jae Ho Choi ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 245~253
The properties of polyethylene materials exhibit good insulation and radiation resistance, but exhibit poor flame resistance. Flame retardant properties of the polyethylene were improved by the radiation induced grafting or crosslinking. When the various flame retardants were fixed onto polyethylene, the amount of fixation in grafting was increased with the increase of radiation dosages. In the case of grafting, it is necessary for high grafting yield that the polyethylene films were swelled before irradiation with
-rays or electron beams. It is the suitable method for the fixation of flame retardant that polyethylene samples were blended with various flame retardants at 1
and then blended polymers were crosslinked by the electron beams at room temperature.
Paper Electrophoretic Separation of Fission Products
Byung Hun Lee ; Jong Du Lee ; Young Kuk Kim ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 254~263
Paper electrophoretic separation of fission products has been carried out by using the specially designed migration apparatus. In general, the isolation of rubidium, strontium, zirconium, ruthenium, cesium, cerium, molybdenum, and some short-lived fission products is more efficient under 0.1M HCl electrolyte as compared with 0.1M NaOH electrolyte. In addition to Np-239, 1-131∼135 were, in particular, observed with different iodine chemical species obtained by the paper-electrophoretic separation of short, neutron-irradiated uranyl nitrate solution.
Calculation of Nuclear Characteristics of the TRIGA Mark-III Reactor
Chong Chul Yook ; Gee Yang Han ; Byung Jin Jun ; Ji Bok Lee ; Chang Kun Lee ;
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 264~276
A simulation procedure which can represent time-dependent nuclear characteristics of TRIGA Mark-III reactor is developed. CITATION, a multi-group diffusion-depletion program, has been utilized as calculational tool. The group structure employed in this study consists of 7 groups: -3-fast and 4-thermal-which is conventionally utilized in TRIGA type reactor analysis. Three-dimensional nuclear characteristics are synthesized by combining results from two-dimensional plane calculation and two-dimensional cylinder calculation, since direct three-dimensional approach is not yet possible. An effort ia made to develope a method which can extract effective zone and group dependent bucklings by neutron diffusion theory rather than conventional zone and/or group independent Ducklings by neutron transport theory, since neutron leakage is quite high for small core such as research reactors. It is turned out that the method developed in this study gives satisfactory results. The calculation is performed under assumptions that all control rods are fully withdrawn, that no samples are inserted in the irradiation holes and that the core is located in the center of the reactor pool. Burnup-dependent variation of core excess reactivity, time dependent change of Xe-135 poisoning and reactivity worth of rotary specimen rack are calculated and compared with operation records. Neutron flux and power distribution as well as neutron spectrum in each irradiation .facility are presented.
A Post-TMI Lookat Boiling Water Reactor Plant Protection
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 277~289
Development Guidelines of Industrial Technology for Less Developed Countries
Nuclear Engineering and Technology, volume 13, issue 4, 1981, Pages 290~306