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 2, Issue 4 - Dec 1970
Volume 2, Issue 3 - Sep 1970
Volume 2, Issue 2 - Jun 1970
Volume 2, Issue 1 - Mar 1970
Selecting the target year
A Study of the Thermoluminescent Properties of Korean Natural Quartz for Possible Use in Gamma-ray Dosimetry
Lee, Hee-Yong ; Kim, Hi-Gyu ; Lee, Chul ;
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 229~239
Various thermoluminescent properties of Korean natural quartz for possible use in
-ray dosimetry has been studied. If the heating is exactly linear,
-irradiated radiation sensitive (type 1)
-quartz can yield a glow curve of single peak, hence glow peak height could be taken as a
-dose for its dosimetry. Quartz crystal dosimeter exhibited the linearity of thermoluminescent intensity in the range from about 2
R to 2
R, and also had an advantage of low fading because of the high peak temperature (300
). The pulverized quartz sample having the grain size of 0.3<ø<0.9mm showed the linearity of T. L. intensity in the range from 50R to 2
R. Therapeutic application of the pulverized sample on the correct measurement of the absorbed dose in a body region of a cancer patient seems to be successful.
Total Cross Sections for Kilovolt Neutrons of Even-Odd Nuclei in the Region of the 3s Strength-Function Resonances
Mann-Cho ; Bak, Hae-Ill ; F.H. Frohner ; K.N. Muller ;
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 241~248
Neutron total cross sections of seperated isotopes were measured with the time-of-flight spectrometer at the 3 MeV Karlsruhe Van do Graaff Accelerator. The neutron energy ranged from 10 to 250 keV. The energy resolution was between 0.2 and 0.5 nsce/m. The measured cross sections were-shape-analyzed in terms of an R-matrix multilevel formula. Thus neutron widths and spins for up to 50 resonances per isotope could be determined. Average neutron widths, level densities and strength functions were derived. The spin dependence of strength functions and the distribution of widths and spacings were investigated.
Pulsed Energy Dependent Neutron Transport Theory
Minn, Hokee ;
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 249~254
A time-energy transient characteristics of pulsed neutron transport problem with an inelastic kernel in the fast domain is solved exactly with a continuous energy transfer operator. A discrete time eigenvalue is found which is asymptotically dominant. The complete solution consists of three parts: a time-energy separable mode which is asymptotically dominant and a non-separable mode which is made up by two parts； a pure energy slowing-down transient and a mixture of time and energy transient which is negligible asymptotically.
General Energy-Dependent Transport Equation with Fission
Lee, Un-Chul ; Pac, Pong-Youl ;
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 255~262
More detailed calculations of extension to general anisotropic transport equation with fission are studied. These calculations involve that the operator can be splitted into scattering and fission operators when we prove the completeness of general anisotropy. Applying these operators to the equation makes it easy to extract the slowing-down transient of zero-measure, and completely solves the transport equation. In addition, the number of the eigenvalues of the second anisotropy is classified with Cs unknown, B
Green's Function of Time-Energy Dependent Neutron Transport Equation
Hokee Minn ; Pac, Pong-Youl ;
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 263~268
The spectrum of continuous transfer operator arising in a time-energy dependent neutron transport equation is analyzed. Four theorems concerning on the spectrum are proved. A convolution theorem of the generalized Mellin energy transform is given. Also the completeness theorem necessary for a final solution is proved. A unique time decay constant 1 - c is found, which is dominant asymptotically.
-Activated LiF Powder
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 269~272
Thermoluminescence (TL) from LiF powder of purity 99.98 ％ was accomplished and this TL intensity showed glow peaks at 12
. Sintered LiF powder which has an activation of 2％ proportion by weight of MgC1
show strong increased TL and this characteristic of the glow curve was investigated precisely. LiF which is used in TL dosimetry has been known to have electrons caused by impurities such as Mg, Mn, etc. This experiment shows that Mg, one of the impurities, is definitely diffused through LiF crystals. The effects of sintering time were detected in this glow curve and it was confirmed that MgC1
also has a TL effect.
Determination of % Contents of Uranium and Thorium in Natural Radioactive Ores by
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 273~278
The Contents of uranium and thorium in radioactive ores produced in Korea were determined by gamma-ray spectrometry utilizing Ge (Li) diode detector. Both methods, namely, gamma-ray spectrometries of activated samples and non-activated samples, were tested and compared for their accuracies and rapidness in determination of contents. Also the useful-ness of application of Ge(Li) diode detector to the determination of uranium and thorium contents in ores was discussed in detail.
Strengthening of Steel by Small Addition of Nb. V. etc.
Imai, Yunoshin ; Shono, Yoshio ;
Nuclear Engineering and Technology, volume 2, issue 4, 1970, Pages 279~287
An an element vanadium is most effective and next is noibium to strengthening the low carbon steels by small addition both on fine precipitation and five grain. The combination effect of vanadium plus niobium or vanadium plus molybdenum is much more effective than adding on element.