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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 9, Issue 2 - Dec 1984
Volume 9, Issue 1 - Jun 1984
Selecting the target year
Characteristics and Applications of Soild State Nuclear Track Detectors -The Detection and Dosimetry of N-Ions by CR-39-
Kang, Yung-Ho ; Kim, Do-Sung ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 55~60
The optimum etching condition of allyl diglycol carbonate (CR-39) for detecting the 60 MeV N-ions was determined as
, 20% NaOH for 130min, by considering the variations of track density and diameter. Under these conditions, the maximum detectable track density was
. Track densities were linearly increased with increase of the total charge of the incident 60 MeV N-ions. By considering the scattring of N-ions as the Rutherford elastic scattering of point source, the measured relative probability was well consistent with the calculated value. The detection efficiency of CR-39 was in the range of 54-41% for 60 MeV N-ions of 12 nC-100 nC.
Characteristics of Alpha Particle Track on Cellulose Nitrate Film
Do, Jin-Yeol ; Jun, Jae-Shik ; Hwang, Sun-Tae ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 61~66
A study on the characteristics of
-particle track on cellulose nitrate film was carried out with a particular emphasis on the dependence of track diameter upon chemical etching condition. The track diameters etched in KOH solution appeared to be, on average, three times larger than those etched in NaOH under the same etching condition. The relationship between the track diameters and both etching time and the energy of incident
-particles was also investigated. It is shown that the particle fluence rate is fairly independent of etching time as far as the condition of irradiation remains unchanged.
Effects of High Dose Irradiation on The Leukocyte Life Span
Koh, Joo-Hwan ; Chong, In-Yong ; Kim, Yong-Kyu ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 67~75
As a part of studies on acute effects of high dose irradiation the present report was carried out to evaluate the changes of the leukocyte life span in the Newzealand white male rabbits by a single whole body exposure to gamma rays from
teleirradiation unit. The exposure was done in dose levels of 100, 300, 550 and 1,000 rad to each experimental group of 10 rabbits. The life span and apparent half survival time of leukocytes, and the elution rate of leukocytes in the circulating blood were measured by McMillan method using
. 1. As a critical indicator of radiation hazards of the Newzealand male rabbits, the LD 50/30 and LD 100/30 after whole body exposure was estimated as 550 and 1,000 rads respectively. 2. The life span of leukocyte in the circulation after irradiation was slightly shortened in the 100 rad irradiated group, as compared with the unirradiated control group, but markedly shortened in the 300, 550 and 1,000 rads irradiated group. 3. After irradiation, decrease of leukocyte half survival time in the circulation showed the same pattern as that of leukocytes life span. 4. As the irradiation doses increased, the elution rate of
tagged leukocytes in the circulation were markedly increased gradually. 5. The life span shortening of leukocytes in the circulation after irradiation seems to occure by two processes of senescence acceleration and early destruction.
Comparative Study on the Committed Dose Equivalent for Adults and Infants
Sung, Kye-Yong ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 76~89
Weighted committed dose equivalents(
) per intake of unit activity of four nuclides-I-131, I-133, Cs-134 and Cs-137-, which was based on the concepts of ICRP Pub. 30, are calculated for adult who is 70 kg and 25 years old and, for infant who is 10 kg and 1 year old. Metabolism of iodine taken through oral or inhalation pathway is described by using the three-compartment model which consists of inorganic, thyroid and organic compartment. After intake, the amount of iodine in every compartment is calculated by solving the transfer equations among the these compartments. As soon as caesium is taken into the body, it is distributed uniformly in the body through the transfer compartment. In this case, the amount of caesium in total body is calculated by using the total body compartment model which is divided into two tissue compartments because of their different biological half-lifes of caesium in body. As a result of calculations, whether oral or inhalation pathway, the values of (
) per intake of unit activity of I-131 for infants are about ten times as much as those of adults. On the other hand, for Cs-134 and Cs-137, the values of
per intake of unit activity show that, whether adults of infants, they have almost the same values.
Radiation Shielding Analysis on The Spent Fuel Storage Facility for the Extended Fuel Cycle
Lee, Tae-Young ; Ha, Chung-Woo ; Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 90~96
Estimated dose rates in spent fuel pool storage with the extended fuel cycle core management were reviewed and compared with design limit after calculation with the aid of DLC-23/CASK(22 n, 18 g) nuclear data and ANISN code. Radioactivity and gamma spectrum within spent fuel assemblies were calculated with ORIGEN code by extended fuel cycle model. In the calculation of dose rate, the fuel pool geometry was assumed to be infinite slab. Also, composition materials and radiation source within assemblies which are being stored in pool storage were assumed to be uniformly distributed throughout all the assemblies. As a result of culculation of dose rate from stored assemblies and waterborne radionuclides in pool water, the calculated dose rates appear to be lower than design basis limit under normal condition as well as abnormal condition.
Criticality Analyses of Spent Fuel Shipping Cask
Min, Duck-Kee ; Ro, Seung-Gy ; Kwack, Eun-Ho ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 97~102
Criticality analyses of the KSC-1(Korean Shipping Cask-1) spent fuel shipping cask have been performed with the help of KENO-IV Monte Carlo computer code and 19-group CSLIB 19 cross section set which was generated from AMPX modular system. The analyses followed a benchmark calculation which has been made regard to the B & W CX-10 criticality facility in order to validate the Monte Carlo code cross section set described above. The KSC-1 shipping cask seems to be safe in the criticality point of view for the transport of one PWR spent fuel assembly under the normal conditions as well as the hypothetical accident conditions.
A Convenient Method on the Methyl-Ethyl-Ketone Extraction of
Lee, Jong-Du ; Lee, Byung-Hyn ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 103~111
A convenient method of
-methyl-ethyl-ketone (MEK) extraction technique was developed and a mobile
-extraction generator was designed. The MEK extraction and the phase separation of
were carried out with a simple procedure in the same container. The shielding of
radioactivity was made with one lead container. The system was simplified by shielding
extract was recovered by adsorption and elution only, and therefore, the possibility of volatilization was reduced. The volume of
-saline product was reduced to 1 ml by using a small alumina column and the column operation time was shortened. The separation time of
was reduced to 30 minutes, and the operation was carried out at the outside of the shielding. The system was designed to operate under the condition of bacteria-free.
An Experimental Study on Airborne Contamination and Decontamination for
Chu, Sung-Sil ; Park, Chang-Yun ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 112~117
A lot of radioisotopes are applied to medical fields. It's very important to measure the activities on airborne radioiodine discharged in air from
solutions and from patients treated with radioiodine. Also surface decontamination is another one important problem to be completly solved in the isotope laboratory where there is always the possibility of radiation contamination. The Authors measured the activities on airborne radioiodine with RI collector and scintillation counter. 1. The mean accumulative activity of airborne radioiodine discharged into air from
solution was measured as
rate, and the maximum value was
. 2. Radioactivity rate per hour of airborne iodine discharged into air from patients treated with
was measured as
at 8 hour after administration of radioiodine and decreased into
after 24 hour. 3. Metalic surfaces such as stainless steel or aluminum are decontaminated 5 to 6 times more rapidly than wood and concrete surfaces. 4. Decontamination with wet wiping with detergent was 9 to 10 times more rapidly than dry wiping method, but dry wiping was useful for the first step to prevent spreading and flowing from liquid radioactive materials.
The Experience and Analysis of Radiological Protection at KoRi Unit #1, Nuclear Power Plant
Park, Shin-Woo ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 118~128
The analysis of radiological protection at Kori Nuclear Unit #1, which started commercial operation on April 29, 1978, has been carried out in three areas, namely, radiation exposure, radioactive waste disposal and environmental management. The analysis results for radiation exposure and radioactive effluent releases appear to increase gradually with plant operating years. On the other hand, the apex of radiation exposure and radioactive effluent releases was in 1983 and 1982 respectively and then decreased or stabilized. Also, the operation environmental radioactivity seems to be no higher than preoperation environmental radioactivity.
Recent Trend of Radiation Protection Research and Education in Wersten Countries
Jun, Jae-Shik ;
Journal of Radiation Protection and Research, volume 9, issue 2, 1984, Pages 129~136
It is a report on the recent trend of research and educational activities in the field of radiation protection in western countries perceived by the author through the participation to the 6th International Congress of IRPA held in Berlin(West) from May 7 to 12, and the IAEA scientific visit to several universities and a couple of national laboratories in the United States from August 27 to September 10, 1984.