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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 10, Issue 2 - Dec 1985
Volume 10, Issue 1 - Jun 1985
Selecting the target year
Sorption Behavior of Cesium-137, Cerium-144 and Cobalt-60 on Zeolites
Kim, Seok-Chul ; Lee, Byung-Hun ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 3~13
The sorption behavior of some typical fission products such as Cs-137, long-lived radionuclide; Ce-144, rare-earth element; and Co-60, corrosion product on zeolite A, zeolite F-9 (faujasite) and amorphous zeolite was determined with the salt concentrations, 0.01 M- to 2.0 M- nitric acid and ammonium nitrate, and the shaking time, 15 minutes interval from 15 minute to 90 minute. Kd values were obtained through the batch experiment. In conclusion, the optimal conditions for isolation and removal of the typical radionuclides are as following: zeolite, amorphous zeolite; concentration,
; pH4; shaking time, one hour; the most effective species, Cs-137.
Development of Monoenergetic Photon Source in the Energe Range below 100 keV by the X-ray Fluorescence Method
Lee, Youn-Myoung ; Lee, Kun-Jai ; Hah, Suck-Ho ; Hwang, Sun-Tae ; Lee, Kyung-Ju ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 14~28
The development of mono energetic photon sources using
fluorescence X-ray of pure material was carried out in the energy range below 100 keV. The monoenergetic photons are very useful in the calibration of the radiation measuring instruments and can be produced as the
fluorescence X-ray by irradiating the bremsstrahlung to the thin pure metal foils called ‘radiators’. In this experiment, several radiators such as
provide the wide monoenergetic photon energy ranging from 20 keV to 80 keV. By the spectrometry with HpGe LEPS, spectral purity factors which measure the monochrometicity for the
fluorescence X-ray, were determined as
. Dosimetry for the purpose of the determination of the exposure rate with a 600cc thin window ionization chamber, which was calibrated by the standard free-air ionization chamber, was performed. Exposure rates ranging
was obtained according to the
fluorescence X-ray energy for each radiator.
Studies of the Radiation Effects on Mouse Germ Cell
Chung, Kyu-Hoi ; Chun, Ki-Jung ; Chung, Hai-Won ; Yoo, Byung-Sun ; Lee, Jeong-Ho ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 29~40
The objectives of present study is to investigate genetic damage of radiation in mammalian male germ cell and. to establish available screening method for determining genetic hazard by radiation. Several methods were employed to measure the genetic damage of radiation as follows: Sperm head counts, frequency occurrence of sperm with abnormal head shape, fertility, activity of LDH-X, and the induction of unscheduled DNA synthesis (U.D.S.) in male mouse were performed with the passing of time after irradiation by making use of the sequence of event that occurs during spermatogenesis. Sperm head counts and activity of LDH-X in testes were gradually reduced by increased radiation dose and with the passing of the time after irradiation. Frequency occurrence of sperm with abnormal head shape, sterile period, and the induction of unscheduled DNA synthesis were increased by increased radiation dose. It is suggested that since germ cell is a direct reflection of genetic complement, the use of male germ cell is rapid and convenient method for measuring genetic damage by radiation.
Neutron Streaming Analysis in 1300 MWe Pressurized Water Reactor Cavity
Kwon, Seog-Guen ; Kim, Kyung-Eung ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 41~49
Neutron Streaming analysis in 1300 MWe pressurized water reactor cavity was performed. In this calculation, the discrete ordinates transport codes, ANISN and DOT 3.5, and the Monte Carlo code, TRIPOLI-02 were used with the coupling code, DOTTRI. In this study IBM 3033 type computer was used. The calculated neutron fluxes and dose rates were compared with the measured data in a 900MWe pressurized water reactor cavity to show a good agreement, although some deviations in the results for each energy group were noticed. These results will be applied in the radiation shielding design of high capacity nuclear power reactors and, to the means of radiation protection in case of the reactor maintenance and the access of the reactor cavity.
Establishment of Release Limits for Airborne Effluent into the Environment Based on ALARA Concept
Lee, Byung-Ki ; Cha, Moon-Hoe ; Nam, Soon-Kwon ; Chang, Si-Young ; Ha, Chung-Woo ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 50~63
A derivation of new release limit, named Derived Release Limit(DRL), into the atomsphere from a reference nuclear power plant has been performed on the basis of the new system of dose limitation recommended by the ICRP, instead of the (MPC)a limit which has been currently used until now as a general standard for radioactive effluents in Korea. In DRL Calculation, a Concentration Factor Method was applied, in which the concentrations of long-term routinely released radionuclides were in equilibrium with dose in environment under the steady state condition. The analytical model used in the exposure pathway analysis was the one which has been suggested by the USNRC and the exposure limits applied in this analysis were those recommended by the USEPA lately. In the exposure pathway analysis, all of the pathways are not considered and some may be excluded either because they are not applicable or their contribution to the exposure is insignificant compared with other pathways. In case, the environmental model developed in this study was applied to the Kori nuclear power plant as the reference power plant, the highest DRL value was calculated to be as
for Kr-85 in external whole body exposure from the semi-infinite radioactive cloud, while the lowest DRL value was observed 3.64Ci/yr for Co-60 in external whole body exposure from the contaminated ground, by the radioactive particulates. The most critical exposure pathway to an individual in the unrestricted area of interest (Kilchun-Ri, 1.3 km to the north of the release point) seems to be the exposure pathway from the contaminated ground and the most critical radionuclide in all pathways appears to be Co-60 in the same pathway. When comparing the actual release rate from KNU-l in 1982 with the DRL's obtained here the release of radionuclides from KNU-1 were much lower than the DRL's and it could be conclued that the exposure to an individual had been kept below the exposure limits recommended by the USEPA.
Methylene blue-PVA Dosimeter
Chung, W.H. ; Kim, H.S. ; Kim, H.J. ; Jung, H.T. ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 64~66
A methylene blue-PVA system has been tested as a krad range dosimeter. Mb dye films were fabricated by casting PVA in solution with the methylene blue. In the air the system was irradiated by X-ray and the decolorisation of the dye film was found to remain unchanged for sufficiently long time. The radiation response on optical density at 670 nm in the Mb-PVA system shows a quite good linearity and reproducibility in the krad range.
Radioactive Neutron Source Calibration at the Korea Standards Research Institute
Hwang, Sun-Tae ; Choi, Kil-Oung ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 67~73
The manganous sulfate bath method for neutron source calibrations at the K-SRI is described together with the measurement of neutron emission rate of a source and the corrections applied for capture by competing nuclei of neutrons, and thermal neutron leakage, neutron absorption in the source itself. The commercially available neutron sources (Am-Be,
) for the calibration checks of neutron radiation instruments in the MeV range are considered in this paper.
The Underlying Concept of the ICRU Report 39
Lee, Jai-Ki ;
Journal of Radiation Protection and Research, volume 10, issue 1, 1985, Pages 74~85
The four new operational quantities for the practical determination of dose equivalents from external radiation sources, defined in the ICRU report 39, are reviewed from the viewpoint of the underlying concept, the relationship to the existing quantities, and the expected role in the radiation protection practice and in the radiation measurements.