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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 12, Issue 4 - Dec 1980
Volume 12, Issue 3 - Sep 1980
Volume 12, Issue 2 - Jun 1980
Volume 12, Issue 1 - Mar 1980
Selecting the target year
Enzymatic Radioiodination of Insulin for Radioimmunoassay Use
Awh, Ok-Doo ; Kim, Jae-Rok ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 81~87
Insulin was labelled with
I using lactoperoxidase as an oxidizing agent. The reaction product was purified via two stages: a starch gel electrophoresis(SGE) and a Sephadex gel filtration (SF). Upon comparison of the labelling yields and the bindabilities of the labelled insulin to its antibody, it has been found that the enzyme method shows higher yields (50%) and the better bindability to its antibody than the conventional chloramine-T method (35%). By checking the insulin blank labelling mixture with a SGE, a paper chromatography, and a radioautography technique, a by-product in the lactoperoxidase method has been identified. The separated fractions in SGE and SF were also analyzed and discussed.
Investigation of Molten Fuel Relocation Dynamics with Applications to LMFBR Post-Accident Fuel Relocation
Chun, Moon-Hyun ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 88~98
The process of solidification of a single-phase flowing hot fluid in a cylindrical tube has been investigated analytically and experimentally. A series of tests were performed, using paraffin -wax and Wood's metal as flowing hot fluids. These data verified the existing quasistatic numerical analysis model of freezing process developed at Brookhaven National Laboratory In addition, experimental results provided information regarding the effects of various parameters on the .process of transient flowing and freezing through a vertical channel. The experimental apparatus and techniques are described. Comparison of experimental data with predictions of mathematical models for transient molten fluid displacement are presented in graphical form. In addition, the mathematical model is applied to LMFBR post-accident conditions.
Recoil Effects of Neutron-irradiated Metal Salts
Lee, Byung-Hun ; Lee, Jong-Du ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 99~105
The distribution of
Cl recoil species following radiative neutron capture in permanganates, chlorates and perchlorates has been investigated by using ion-exchange chromatography method. The whole of the
Mn radioactivity in permanganates appeared in two valence states, the
Cl radioactivity in chlorates in two valence states and also the
Cl radioactivity in perchlorates in three valence states. Recoil energy was calculated. The internal conversion of
Cl isomer transition affects the retention value. The greater the radii of the cation, the higher is the probability of the recoil atom breaking through the secondary cage. In ammonium salt, the ammonium ion behaves as a reducing agent. Crystal structures with their greater free space have shown low retention.
A Study on the Radiometric Method for the Determination of Uranium and Thorium in Ores
Lee, Chul ; Lee, Keun-Min ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 106~110
The radio-equilibrium conditions of uranium and thorium in the Okcheon black shales and monazites have been studied. As the results. a radiometric method based on the measurements of gamma ray activity has been suggested for the simple analysis of many samples in the process of the prospecting and the grading of uranium and thorium minerals.
Some Studies on Physics Parameters of Wolsung Unit No. 1
Kim, Seoung-Yun ; Kim, Bong-Ghi ; Kim, Dong-Hoon ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 111~120
Nuclear physics parameters of the Wolsung CANDU-PHW reactor are computed by use of the PHWCELL computer code that is an improved version of LATREP. The PHWCELL code mainly computes cell parameters of heavy water moderated reactors, and modeling scheme of heavy water reactor cell calculations has been developed with the PHWCELL computer code. The reactor operating conditions considered in the study are cold zero power (CZP) and hot full power (HFP) with equilibrium poison. The cell parameters are also computed as a function of fuel burnup and the numerical results are compared with the results in PSR of the Wolsung unit and in the previous study.
Selection of Well Labelled Insulin Fractions for Radioimmunoassay Use
Awh, Ok-Doo ; Kim, Jae-Rok ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 121~126
Selection methods of well labelled insulin fractions based on two different criteria were compared to establish an efficient low level RIA of insulin and to elucidate the correlation between the immunoreactivity and the charcoal-adsorptivity of the radioiodine labelled insulin. The results indicated that the selection of well labelled insulin fractions by means of a charcoal-adsorption test is inappropriate. Generally, the distribution of radioactivity antibody-bindability, and charcoal-adsorptivity of the labelled insulin was not consistent with each other. Thus. the selection should be carried out for every labelling batch to get the utmost assay reliability by antibody-bindability but not by charcoal-adsorptivity. By using the well selected labelled insulin fractions based on antibody-binding, a correct assay for a reference serum was possible, and by extending the incubation time upto 96 hrs, a sharp dose response curve could be obtained even in the range of below 5
U/ml standard insulin doses.
Neutron Streaming and PWR Cavity Shielding Design
Kim, Kyo-Sool ; Lee, Chang-Kun ;
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 127~134
Shielding problems associated with neutron streaming through the reactor vessel cavity of pressurized water reactors are discussed to a certain extent with the actual examples in the currently operating reactors. Various remedial techniques are proposed herein to mitigate the tedious neutron streaming phenomena including piling up in heaps of temporary boron-containing bags and the installation of permanent shield structure making use of a certain refractory materials. In conclusion, optimum cavity shielding design concepts are presented with special emphasis on such major factors as the identification of major neutron streaming path, selection of necessary shielding materials with acceptable constraints, detailed design characteristics and physical configuration as well as the formulation of dependable mathematical tools to predict the final outcome of each design concept proposed in the context.
TMI 교훈과 향후-원자력 안전과제
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 135~136
Development Guidelines of Industrial Technology for tess Developed Countries
Nuclear Engineering and Technology, volume 12, issue 2, 1980, Pages 137~151