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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 18, Issue 2 - Nov 1993
Volume 18, Issue 1 - Jun 1993
Selecting the target year
Chromosomal Aberrations Induced in Human Lymphocytes by in vitro Irradiation with
Ahn, Yong-Chan ; Ha, Sung-Whan ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 1~16
As guides to decision-making in the management of the victims in case of acute whole body or partial body radiation exposure, we studied the relationship between radiation dose and the frequency of chromosomal aberrations observed in peripheral lymphocytes that were irradiated in vitro with
at doses ranging from 2Gy to 12Gy. The yields of cells with unstable chromosomal aberrations (dicentric chromosomes, ring chromosomes, and acentric fragment pairs) were 32% at 2Gy, 47% at 4Gy, 80% at 6Gy, 94% at 8Gy, and 100% at 10Gy and over. Ydr, which reflect average dose to the whole body in case of acute whole body exposure, were 1.373 at 2Gy, 0.669 at 4Gy, 1.734 at 6Gy, 2.773 at 8Gy, 3.746 at 10Gy and 5.454 at 12Gy. The relationship between radiation dose (D) and the frequency of dicentric plus ring chromosomes per cell(Ydr) could be expressed as
. Qdr, which are used in estimating dose of partial body exposure and dose of past exposure, were 1.166 at 2Gy, 1.436 at 4Gy, 2.173 at 6Gy, 2.945 at 8Gy, 3.746 at 10Gy and 5.454 at 12Gy. To see how confidently this dosimetry system may be used, we obtained Qdr values from those who received one fraction of homogenous partial body irradiation of 1.BGy, 2.5Gy, and 7.OGy therapeutically; in vivo Qdr values were 1.109, 1.222 and 2.222 respectively. The estimated doses calculated from these in vivo Qdr values using the equation
were 1.52Gy, 2.48Gy, and 6.54Gy respectively, which were very close to the doses actually given.
Simulation of Beta Ray Spectra in Liquid Scintillation Counting System by means of Monte Carlo Method
Yi, Chul-Young ; Jun, Jae-Shik ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 17~25
Beta ray spectra of
in liquid scintillation counting system have been calculated using the Monte Carlo method by which physical behaviors of particle transport in medium were simulated. The calculations have been carried out on the basis of beta rays being slowing down according to the continuous slowing down approximation(CSDA) model. Beta rays generated in simulation geometry were traced until they lost their energy below 0.3keV that in known to be the detection limit in the liquid scintillation counter. Scintillator solution in which pure beta emitting radionuclides were dissolved uniformly was assumed to be bottled in the shape of right circular cylinder with 12.5mm in radius and 35mm in height. The comparison of the calculated and measured results showed satisfactory agreement between those two, with slight discrepancy due to self quenching in the case of lower energy of emitted beta particles in the solution.
Radiation Shielding Analysis of CANDU Spent Fuel Transport Cask
Choi, Jong-Rak ; Yoon, Jung-Hyun ; Kang, Hee-Young ; Lee, Heung-Young ; Chung, Sung-Whan ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 27~35
A shielding analysis of the shipping cask for transporting the CANDU spent fuel bundles has been studied. Radiation source term has been calculated on spent fuel with burn-up of 7,800 MWD/MTU and 5 years cooling time by ORIGEN2 code. The shielding calculation for the cask capable of transporting 378 bundles of CANDU spent fuel has been made by use of 1-D ANISN and 2-D DOT 4.2 codes. As a result of analysis, the optimum shield thickness of cask was obtained. And it is proved that the safety in radiation shielding under normal transport and hypothetical accident conditions is confirmed to satisfy the allowable values specified in IAEA Safety Series No. 6 and the Korean Atomic Law.
Serum enzymes as indicators of radiation exposure in rat
Kim, In-Gyu ; Kim, Sang-Bok ; Kim, Jin-Gyu ; Kim, Kug-Chan ; Chun, Ki-Chung ; Park, Hyo-Kook ; Lee, Kang-Suk ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 37~45
Enzyme activity changes in rat blood as biochemical indicator useful for evaluating exposure dose were experimentally studied. The experimental results obtained are as follows: 1) Alkaline phosphatase activities increased in the blood serum until 24 hours after 0.1, 0.25, 0.5, 2 and 4Gy irradiation and its activities returned normal condition after 72 hours of post-irradiation. Creatine kinase activities increased in the blood serum until 72 hours after 2 and 4Gy irradiation but any significant activity changes were not detected after 0.1, 0.25Gy irradiation. 2) Malate dehydrogenase activities did not reveal available changes after 0.1, 0.25, 0.5 Gy irradiation and lactate dehynrogenase activities decreased in the blood serum after 0.1, 0.25, 0.5 Gy irradiation.3) Glutamate oxaloacetate transaminase activity changes were detected in the blood serum after 0.1, 0.25, 0.5, 2, 4Gy(0.1Gy/min.) and GOT activities increased after 0.5, 1, 1.5, 2, 3, 5, 7Gy(0.5Gy/sec.). Any acid phosphatase activities were detected in the blood serum after 0.1, 0.25, 0.5, 2, 4Gy(0.1Gy/min.) and 0.5, 1, 1.5, 2, 3, 5, 7Gy(0.5 Gy/sec.) irradiation. Potentially some of these enzymes can be used as indicator protein for radiation injury. Futher investigation is needed to find better biochemical indicators utilizing recent know-ledge and techniques of biochemistry.
Analysis of the criticality of the shipping cask(KSC-7)
Yoon, Jung-Hyun ; Choi, Jong-Rak ; Kwak, Eun-Ho ; Lee, Heung-Young ; Chung, Sung-Whan ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 47~59
The criticality of the shipping cask(KSC-7) for transportion of 7PWR spent fuel assemblies has been calculated and analysised on the basis of neutron transport theory. For criticality analysis, effects of the rod pitches, the fixed neutron absorbers(borated sus+boral) were considered. The effective multiplication factor has been calculated by KENO-Va, Mote Carlo method computer code, with the HANSEN-ROACH 16 group cross section set, which was made for personal computer system. The criticality for the KSC-7 cask was calculated in terms of the fresh fuel which was conservative for the aspects of nuclear critility. From the results of criticality analysis, the calculated Keff is proved to be lower than subcritical limit during normal transportation and under hypothetical accident condition. The maximum calculated criticalities of the KSC-7 were lower the safety criticality limit 1.0 recommended by US 10CFR71 both under normal and hypothetical accident condition. Also, to verify the KSC-7 criticality calculation results by using KENO-Va, it was carried out benchmark calculation with experimental data of B & W(Bobcock and Wilcox) company. From the 3s series of calculation of the KSC-7 cask and benchmark calculation, the cask was safely designed in nuclear criticality, respectively.
Enzyme activity changes by intraperitoneal injection of uranium in the carp liver
Kim, In-Gyu ; Kim, Kug-Chan ; Kim, Jin-Kyu ; Kim, Sang-Bok ; Chun, Ki-Chung ; Park, Hyo-Kook ; Lee, Kang-Suk ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 61~69
We examined various enzyme activity changes by intraperitoneal injection uranium in the carp liver. These enzyme activity changes can be used as biochemical indicators of internal exposure to uranium. The results were followings ; 1) Total protein concentration decreased by intraperitoneal injection in the carp liver. 2) Lysosomal acid pretense and
activities increased in the liver until sixth intraperitoneal injection of uranium, but Lysosomal acid phosphatase activities decreased in the liver until the sixth injection of uranium. 3) Alkaline phosphatase activities sharply increased and Glutamate oxaloacetate Transaminase activities steadily decreased in the liver until the sixth injection of uranium. 4) Creatine %kinase activities steadily decreased and malate dehydrogenase activities sharply decreased in the liver after the primary injection of uranium. Any malate dehydrogenase activities was not detected after sixth injection of uranium.
Anisotropy and Dose Equivalents Conversion Factors for the Unmoderated
Jeong, Deok-Yeon ; Chang, Si-Young ; Yoon, Suk-Chul ; Kim, Jong-Soo ;
Journal of Radiation Protection and Research, volume 18, issue 2, 1993, Pages 71~79
Form the pure Maxwellian distribution(kT= 1.42MeV), the effects upon calibration factors of encapsulating a
spontaneous fission neutron source were investigated to establish a standard neutron field in the Secondary Standard Dosimetry Laboratory at Korea Atomic Energy Research Institute(KAERI). A Monte Carlo code MCNP was used in simulating the encapsulation SR-Cf-100 and SR-Cf-1273 to be real conditions. The anisotropy(FI) and fluence-to-dose equivalents conversion factors
were evaluated and compared with other results. As the results, the FI was determined to be 1.061 at
statistical error and the
was evaluated to be
statistical error, which is lower by 1.8% than that recommended by the ISO 8529. This means physically that the neutron spectrum of the unmoderated
source in KAERI is a little more softened than that by the ISO.