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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Journal of Radiation Protection and Research
Journal Basic Information
Journal DOI :
Korean Association for Radiation Protection
Editor in Chief :
Volume & Issues
Volume 4, Issue 1 - Jul 1979
Selecting the target year
Criticality Safety Determination of Spent Fuel Storage Vault
Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 4, issue 1, 1979, Pages 1~4
Effective multiplication factor has been calculated for one PWR fresh fuel assembly immersed in a spent fuel storage vault on the basis of the neutron transport theory. A numerical calculation has been carried out by means of Sn approximation. The method employed in this study is that the energy domain is broken into 16 groups, the angular variable is divided into four discrete direction, i.e.,
, and the spatial variable which is divided into fine meshes at the interface between different materials is discretized into 27 mesh points. The calculated
value of 0.6145 seems to be far small in comparison with the value obtained by other author for an infinite array of fuel assemblies.
The Measurement of Airborne Radon Daughter Concentrations in the Atmosphere
Ha, Chung-Woo ; Lee, Jai-Ki ; Moon, Philip S. ; Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 4, issue 1, 1979, Pages 5~13
A simple method for determining the airborne concentration of radon daughter products has been developed, which is based on gross alpha counting of the air filter collections at several time intervals after completion of air sampling. The concentration of each nuclide is then obtained from an equation involving the alpha disintegrations, the sampling time, and the known numerical coefficients. The state of radioactive disequilibrium is also investigated. The atmosphere sampled in the TRIGA Mark-III reactor room was largely in disequilibrium. The extent of radioactive disequilibrium between radon daughter products seems likely depend on sampling times associated with turbulence conditions. The data obtained here will certainly provide useful information on the evaluation of internal exposure and calibration of effluent monitoring instruments.
Rapidly and Accurately Processing of Low Melting Block for Shielding of Radiotherapy
Chu, S.S. ; Lee, D.H. ; Park, C.Y. ;
Journal of Radiation Protection and Research, volume 4, issue 1, 1979, Pages 14~20
For accurate and easily shielding irregular shaped organ, its minimized penumbra region and a low melting point alloy 'Lead Y' and synchronizing instrument have been developed. The 'Lead Y' is the quaternary eutectic alloy and it is composed of Lead 30.0% Tin 11.5% Bismuth 48 5% Cadmium 10.0% The density of its at
and the melting temperature has
. The thickness of 'Lead Y' for perfect shielding of Co-60 gamma ray and LINAC 10MeV x-ray is 6cm and 7cm respectively. The 'Lead Y' shielding block is casted directly on the styrofoam from which is cut with hot wire of synchronizer device. The special features and advantages of the Lead Y shielding block could be summarized as follows; 1. The shielding block for radiotherapy is rapidly processed only with boiling water and styrofoam. 2. It is not injure one's health and not danger of a fire, because of not generating of any metals vapor and evil smelling. 3. It is very effective to minimize secondary penumbra for the protection of healthy tissue from unnecessary ionizing radiation regardless of the magnification source to skin distance. 4. The HVL of the Lead Y is 1.2cm for Co-60 gamma ray and it's shielding effect is almost same as the pure lead block. 5. The hardness of Lead Y is 1.5 times higher than lead block. 6. It's reavailability is higher than lead block and then one block of Lead Y is reavailable about 30 to 40 times. 7. It is usefull for shielding of x-ray, gamma ray, beta-ray, electron and neutron radiation. 8. The materials for Lead Y are easy to acquire with reasonable price and tractable.
Calculation of the Air-Scattering Dose Rate by the Single Scattering Approximation
Yook, Chong-Chul ; Ha, Chung-Woo ; Lee, Jai-Ki ; Moon, Philip S. ;
Journal of Radiation Protection and Research, volume 4, issue 1, 1979, Pages 21~28
A calculation is presented of air-scattered gamma rays using the modified single-scattering approximation. The air-scattered tissue dose rates are calculated for a general purpose taking into account (a) the buildup and exponential attenuation, (b) the energy spectrum at the position of question and (c) the geometrical scattering volume in three dimensions. These calculations have been further modified to render them applicable to a typical field irradiation facility which is surrounded by a shield wall and in which the source is fitted with a beam collimating device. The results of the calculation include the energy spectra, angular distribution and tissue does rates at source-receiver separation distances of from 35m to 300m. The comparison shows that the present method developed may be generally adequate for the gamma-ray air-scattering problems in field irradiation facilities if energy and angular distribution at the shield are unimportant.
ALARA for Nuclear Power Plant Operation
Knapp Peter James ;
Journal of Radiation Protection and Research, volume 4, issue 1, 1979, Pages 29~35
Comparison of the risk of death due to radiation exposure with the same risk due to occupational hazards in other safe industries underlines the importance of the ALARA principle. The outlined responsibilities and listed examples presented here can serve as a basis for expanding and developing the concepts necessary for its successful application.
Characteristics of TLD and Their Recent Trend
Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 4, issue 1, 1979, Pages 36~54