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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 6, Issue 1 - Oct 1981
Selecting the target year
Environmental Radiation Level in Korea(
Rho, Chae-Shik ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 1~7
This report presents the results of the environmental radiation program at Korea Advanced Energy Research Institute (KAERI) (
) and its surroundings for the last two decades (January, 1961 through December, 1980). In the 1960s, the monthly mean levels of environmental external radiation encountered ranged from a low of 14.2 microroentgen per hour to a high of 42.2 microroentgen per hour with a mean of 21.7 microroentgen per hour, while in 1970s it ranged from a low of 12.4 microroentgen per hour to a high of 40.8 microroentgen per hour with a mean of 20.4 microroentgen per hour. It may, therefore, be said that environmental radiation dose rates remained almost unchanged for the two decades except for the second half of 1960s and the first half of 1970s during which the off-site and on-site patterns were frequently unlike in form and intensity with appreciable differences between average values. Particular results of interest with respect to the effects of the fallout gamma dose rate on environmental radiation show that elevated levels were encountered in association with the deposits of fresh debris from Chinese and Russian nuclear weapons tests in particular.
Calculation of Neutron and Gamma-Ray Flux-to-Dose-Rate Conversion Factors
Kwon, Seog-Guen ; Lee, Soo-Yong ; Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 8~24
This paper presents flux-to-dose-rate conversion factors for neutrons and gamma rays based on the American National Standard Institute(ANSI) N666. These data are used to calculated the dose rate distribution of neutron and gamma ray in radiation fields. Neutron flux-to-dose-rate conversion factors for energies from
to 20 MeV are presented; the corresponding energy range for gamma rays is 0.01 to 15 MeV. Flux-to-dose-rate conversion factors were calculated, under the assumption that radiation energy distribution has nonlinearity in the phantom, have different meaning from those values obtained by monoetiergetic radiation. Especially, these values were determined with the cross section library. The flux-to-dose-rate conversion factors obtained in this work were in a good agreement to the values presented by ANSI. Those data will be a useful for the radiation shielding analysis and the radiation dosimetry in the case of continuous energy distributions.
Measurement of Radon Daughters' Radioactivities by Using Single Filtering Method
Chang, Si-Young ; Ro, Seung-Gy ; Hong, Jong-Sook ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 25~30
A measurement has been made for the radioactivities (or concentrations) of radon daughters, i.e., RaA, RaB and RaC in airborne dust by means of single filtering method. This is to evaluate the radioactivities in terms of Ci or WL (working level) from gross alpha counts measured in the selected-time intervals after an air sample is taken from a membrane filter paper with a mean pore size of
. This work involves determinations of standard deviation in radioactivities, radioactive equilibrium factor and ratio. It appears that a concentration of total radon daughters is
, depending on the sampling time. Generally the highest concentration was observed around nine o'clock in a day while the lowest value was obtained around seventeen o'clock. Standard deviations based on counting statistics of RaA's, RaB's and RaC's concentrations are
, respectively. It is revealed that the radioactive equilibrium factor is 0.322 while the radioactive equilibrium ratio is of pattern $C_1>C_2>C_3$ in general. Here
stand for concentrations of RaA,RaB and RaC, respectively.
A Comparision of Mghr Prescription to Doses at Ponts A and B in Intracavitary Radiotherapy of Cervix Cancer
Park, Charn-Il ; Ha, Sung-Whan ; Kang, Wee-Saing ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 31~33
The 42 patients with carcinoma of the cervix, performed intracavitary radiotherapy, were analysed the doses at points A and B comparing to the mghr prescription. The doses at points A and B were calculated by PC-12 computer planning system. Correlation coefficienty between doses at points A and B and the mghr prescription are 0.82 (p<0.001) and 0.90 (p<0.001) respectively. The slope of the point A line is 0.70 and the slope of the point B is 0.21. Therefore, the dose at point A is approximately 3/4 the mghr prescription and the dose at point B is approximately 1/4 the mghr precription.
Measurement of Leakage and Design for the Protective Barrier of the High Energy Radiation Therapy Room
Chu, Sung-Sil ; Park, Chang-Yun ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 34~40
The logical development of an optimum structural shielding design and the computation of protective barriers for high energy radiation therapy room, Toshiba 13 MeV. are presented. We obtained following results by comparison in between the precalculating values and actual survey after complete installation of radiogenerating units. 1. The calculating formula for the protective barrier written in NCRP report #34(1970) was the most ideal and economic calculating methods for the construction of barrier and to determine thickness for the meeting requirements of the number of patients of 80-100 in daily treatment. 2. The precalculating values of protective barrier are 5 times more protective than that of actual measurement. It is depending on radiation workload and utilization the datas most sequrely. 3. The dose rate during exposure are 2-10 mR/hr at out of the door and the controll room. 4. The foul smelling and ozone gas production from long exposure of cancer patients cannot be eliminated when the room is ill ventilated.
Calculation of Energy Dependence of Calibration Constants in the Continuous Radioactive Effluent Monitors
Lee, Soo-Yong ; Yook, Chong-Chul ; Ha, Chung-Woo ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 41~44
A method is presented by which precise evaluation of radioactive concentrations in liquid or gaseous effluent released from large nuclear facilities is possible. Calculations have been made of the calibration constants at different energies for a commonly used liquid and gaseous effluent monitors as well. It is expected that the method could be applicable to the particular monitors with different geometrical configuration with simple modifications.
Three Mile Island: Medical and Public Health Aspects of a Radiation Accident
Linnemann Roger E. ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 45~52
The March 1979 accident at Three Mile Island provided physicians specializing in radiation medicine an opportunity to observe the field under conditions never seen before. Since no, injuries occurred at the site or within the community, medical personnel were immediately involved in efforts to allay fear, provide accurate information, and replace labortory resources rendered ineffective by the release in the reactor building. Valuable insights concerning medical emergency planning are derived from the accident; suggestions are made for handling any future mishaps.
On the Standardigation in Radiation Dosimetry
Jun, Jae-Shik ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 53~65
Room Planning and Shielding Barriers for the Diagnostic, Theraputic Apperatus
Chung, I.Y. ; Kim, J.Y. ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 66~77
Dosimetry and Units of Ionized Radiation
Chu, Sung-Sil ;
Journal of Radiation Protection and Research, volume 6, issue 1, 1981, Pages 78~82