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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 12, Issue 2 - Dec 1987
Volume 12, Issue 1 - Jun 1987
Selecting the target year
Central Axis Percentage Depth-Dose in a Water Phantom Irradiated by Conventional X-rays
Kim, Wuon-Shik ; Hah, Suck-Ho ; Hwang, Sun-Tae ; Oh, Jang-Jin ; Jun, Jae-Shik ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 1~11
Central axis percentage depth-doses, P(%), were measured at the points from the 2.5cm depth of reference point to 20 cm depth with 2.5 cm interval. Distance from the X-ray target to the water phantom(
) surface was 1 m, and at this point three different beam sizes of
were used. While the X-ray tube voltage varied from 150 to 250 kV, the tube current remained constant at 5 mA. Absorbed dose rate in water,
, was determined using the air kerma calibration factor,
, which was derived from the exposure calibration factor,
, of the NE 2571 ion chamber. The reference exposure rate,
, was measured using the Exradin A-2 ion chamber calibrated at ETL, Japan. The half value layers of the X-rays determined to meet ETL calibration qualities. The absorbed dose rates determined at the calibration point were compared to the values obtained from Burlin's general cavity theory, and the percentage depth-dose values determined from
showed a good agreement with the values of the published depth dose data(BJR Suppl. 17).
Construction of Multichannel Analyser with Successive Approximation Type ADC
Yook, Chong-Chul ; Oh, Byung-Hoon ; Kim, Young-Gyoon ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 12~25
A basic multichannel analyser (MCA) system have been designed and constructed with the successive approximation type ADC (Analog to Digital Converter). Linear Gate, window, and palse stretcher consist of mainly linear and logic IC's, and are properly combined together to achieve short dead time and good linearity of the system. ADC 1211 (analysing time:
) and S-RAM (static random acess memory) 6264 are used in ADC module. Two 6264 memories are connected in parallel in order to-provide enough counting capacity (
). Interfaced microcomputer Apple II controls this system and analizes the counted data. The system is tested by input pulses between 0V to 10V from oscillator.
On the Etching Condition of Cellulose Nitrate Solid State Nuclear Track Detector (SSNTD)
Myung, Dong-Bum ; Jun, Jae-Shik ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 26~33
An experimental study for an optimum etching of commercialized cellulose nitrate SSNTD, CA 80-15 and LR 115-1 for detecting alpha particles, was carried out. Alt-hough ordinary etching condition of the detectors has been recommended by the producer, a remarkable discrepancy in etching tine was found. The detectors were irradiated with a
alpha source under a known geometrical arrangement. Analysis on the track size as functions of etching time and etchant concentration and comparative examination of theoretically predicted number of tracks per unit area with that recorded on the detectors were made, including a study on the variation of detection efficiency with the effective energy of the incident alpha particles.
Radiation Shielding Analysis for the X-ray Facility
Kwon, Seog-Guen ; Choi, Ho-Sin ; Moon, Philip-S. ; Yook, Jong-Chul ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 34~39
Radiation shielding analysis for a 6MeV X-ray facility was carried out. The primary and leakage radiation for the facility can be evaluated based on the methodology in NCRP No. 49 and 51. The present study deals with radiation scattering analysis for the outside and inside door of the facility based on the albedo concept. The calculated dose rates were compared with the results of MORSE-CG code calculation and the measured data, resulting in a good agreement, even though there existed some deviation for the inside door. These results can be utilized to the radiation shielding design of the medical and industrial X and gamma ray facilities, and to the safety evaluation of these facilities.
Radiological Consequence of LOCA for a 900MWe French PWR
Moon, Kwang-Nam ; Yook, Chong-Chul ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 40~47
The amount of the radionuclide release to the environment during a LOCA and its radiological consequence are assessed, for a 900MWe French PWR which is similar to the KNU 9/10, according to RFS V.1.a, in which the source term has been revised more conservatively after the TMI accident. The assessed result shows that the whole body and thyroid doses at the site boundary(500m) for 2 hours after the release are 66 mrem and 13.5 rem, respectively, and are within the corresponding limits. It is expected, however, that the thyroid dose would exceed the limit if the fraction of the organic iodine is over 10% of the iodine inventory.
Impurity Analysis of Domestic
Introduced to Manganese Bath Method
Hwang, Sun-Tae ; Lee, Kyung-Ju ; Choi, Kil-Oung ; Lee, Kwang-Woo ; Woo, Jin-Chun ; Lee, Ki-Bum ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 48~53
The manganous sulphate bath method is widely used for measurements of neutron source strength. In this study, the analytical chemistry method based on the argon supported inductively coupled plasmas emission spectrometry was used for examining the impurity contents of domestic
the product of Chemical Industry, to induce
Mn reactions. From the analytical results, mainly potassium, cobalt, and zinc as well as trace amounts of cadmium, lithium, etc. have turned out to be the relevant impurities absorbing the neutrons, and the fraction of neutrons absorbed by the total impurities was calculated. The value obtained was about 1.37% of the neutrons captured by manganese.
Correlation Between Exposure Rate and Quasi-Effective Energy of Natural Radiation in Japan -TLD Application-
Nakajima, Toshiyuki ;
Journal of Radiation Protection and Research, volume 12, issue 1, 1987, Pages 54~60
The quasi-exposure rate and the quasi-effective energy of the natural radiation in the field at 47 monitoring points around nuclear power plants have been studied with the pair filter thermoluminescence dosimeter system. The results of the six years observation showed that the relationship between the quasi-exposure rate
, and quasi-effective energy
can be represented as a hyperbolic function:
, where the constants A and B correspond to the quasi-exposure rate of cosmic-rays and the minimum quasi-effective energy of natural radiation, respectively. Furthermore, the constant A is in close agreement with the values obtained by using ionization chambers and scintillation detectors. The constant B is approximately 0.68 MeV, closely corresponding to the mean energy of the photons emitted from natural uranium.