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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 19, Issue 3 - Dec 1994
Volume 19, Issue 2 - Aug 1994
Volume 19, Issue 1 - Jun 1994
Selecting the target year
A Study on the Development of Optimization Procedure for Radiological Protection
Song, Jong-Soon ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 1~11
Considering the variety of application and other factors in performing the optimization of radiological protection, it is necessary to use well-structured optimization procedure. In this study, an optimization procedure for design stage of nuclear power plant was proposed, and applied in the selection of alternatives for reducing occupational radiation exposure. As an aiding technique for decision-making, multi-criteria technique was used. As a result, priorities of alternatives are determined, and a problem of applying this result to real situation is reviewed. The developed procedure for optimization can be extended to other areas such as radioactive waste management, medical use of radiation, etc.
Monte Carlo Calculation of Thermal Neutron Flux Distribution for (n, v) Reaction in Calandria
Kim, Soon-Young ; Kim, Jong-Kyung ; Kim, Kyo-Youn ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 13~22
The MCNP 4.2 code was used to calculate the thermal neutron flux distributions for
reaction in mainshell, annular plate, and subshell of the calandria of a CANDU 6 plant during operation. The thermal neutron flux distributions in calandria mainshell, annular plate, and subshell were in the range of
which is somewhat higher than the previous estimates calculated by DOT 4.2 code. As an application to shielding analysis, photon dose rates outside the side and bottom shields were calculated. The resulting dose rates at the reactor accessible areas were below design target,
. The methodology used in this study to evaluate the thermal neutron flux distribution for
can be applied to radiation shielding analysis of CANDU 6 type plants.
Determination of Derived Release Limits for a CANDU Nuclear Power Plant
Kim, Kyo-Youn ; Hwang, Hae-Ryong ; Kim, Jong-Kyung ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 23~35
A computer code DRL was developed to calculate the derived release limits at CANDU type nuclear power plants. The derived release limits resulting from DRL code is to set guidelines for the release of radionuclides in airborne and water-borne effuents during normal operations of a CANDU type nuclear power plant. The DRL code generally follows the methodology Prescribed in the CSA standard N288.1-M87 and uses the Parameter values recommended in the same standards. The DRL code was used to calculate a set of preliminary derived release limits for the Wolsong NPP.
A Study on the Measurement of the Personal Exposure Dose by Film Badge Dosimeter
Chung, Woon-Kwan ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 37~50
The experimental evaluation of exposure conversion formula using the relationship between optical photo-density, exposure dose and the quality of radiation characteristics of radiation energy to X-ray and
. The film badge dosimeter is analysed by exposure conversion formula which evaluate image fading characteristics for development time and directional characteristics for incident beam angle. In conclusion, exposure conversion formula evaluated of this study is satisfied with quality decision criterion of the film badge dosimeter.
Change of Frequency of Chromosome Aberration by Time Interval after Radiation Therapy
Kim, Mi-Sook ; Yi, Chun-Ja ; Ha, Sung-Whan ; Song, Myung-Jae ; Kim, Hee-Jeun ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 51~68
It is good method to use frequency of chromosome aberration in Lymphocytes for a biological dosimetry in cases of accidental exposure to radiation. But in cases of past exposure, biological dosimetry is limited because the frequency of aberration decreases by time after exposure. To provide a basic data for estimation of past radiation exposure, the changing pattern of frequency of unstable chromosome aberration by time interval after exposure was studied. Observation was made on peripheral lymphocytes of 41 blood samples from 20 patients treated for uterine cervical carcinoma and endometrial carcinoma. The patients received 50.4Gy radiation to whole pelvis. Elapsed times after the completion of radiation therapy were 1 day, 3, 6, 9, 12, 24, 52, 104, 156, 208, 260 and 520 weeks. All the blood sample were microcultured. The Ydr, Qdr and Qdra were calculated from frequency of unstable aberration. Ydr did not decrease for 3 weeks after radiation therapy, and thereafter, decreased very rapidly and reached 0.05 at two years after radiation therapy and decreased very slowly until 5 years after radiation therapy. Relationship between unstable chromosome aberration and time interval after radiation therapy was described as
(time in weeks) Qdr remained constant at 1.51 until 24 weeks after radiation therapy and then decreased to 1.17 at 52 weeks. Therafter, it did not change. Qdra remained constant at 1.10 for 12 weeks after radiation therapy and decreased to 0.81 at 52 weeks. Thereafter, it remained constant. Two superimposed exponential Ydr disappearance rate suggests that it is possible to calculate the past exposure dose. When the elapsed time after exposure is short, Qdr and Qdra are useful papameters for biological dosimetry for past radiation exposure.
Assessment of Thyroid Dose Evaluation Method by Monitoring of I-131 Concentration in Air
Lee, Jong-Il ; Seo, Kyung-Won ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 69~80
The TCMI(Three-Compartment Model for iodine) computer code has been developed, which is based on the three-compartment model and the respiratory model recommended in ICRP publication 54. This code is able to evaluate the thyroid burden, dose equivalent, committed dose equivalent and urinary excretion rate as time-dependent functions from the input data: working time and the radioiodine concentration in air. Using the TCMI code, the time-dependent thyroid burdens, the thyroid doses and the urinary excretion rates were calculated for three specific exposure patterns : acute, chronic and periodic. Applicability as an internal dose evaluation method has been assessed by comparing the results with some operational experiences. Simple equations and tables are provided to be used in the evaluation of the thyroid burden and the resulting doses for given I-131 concentration in air and the working time.
착색 PVA 필름 선량계
Chung, Woon-Hyuk ;
Journal of Radiation Protection and Research, volume 19, issue 1, 1994, Pages 81~93