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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 29, Issue 4 - Dec 2004
Volume 29, Issue 3 - Sep 2004
Volume 29, Issue 2 - Jun 2004
Volume 29, Issue 1 - Mar 2004
Selecting the target year
Ion Exchange Behavior of
on Diphosil, a new ion exchange resin
Kim, Su-Jeong ; Lee, Sang-Jin ; Yang, Ho-Yeon ; Shin, Sang-Woon ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 1~8
Diphosil, a new version of the organic-inorganic composite resin developed by ANL has a structure of the chelating diphosphonic acid groups grafted to a silica support. To apply Diphosil for the treatment of liquid radioactive waste from nuclear power plants, the adsorption equilibrium and column experiments were carried out for the main radionuclides,
, in the liquid radwaste stream. Through the adsorption equilibrium experiments, the removal efficiencies of
, and the effects of non-radioactive ions on the removal efficiency have been measured in various conditions using radiotracers. The breakthrough curves for the tested tracers were obtained from the laboratory scale column tests using the simulated liquid radioactive waste. In addition, the removal capacity of Diphosil is compared with that of Amberlite IRN 77 resin, generally used in nuclear power plants.
Acridine Orange Stained Micronucleus Assay in Human B and T-lymphocytes after Low Dose
Choi, Jeong-Mi ; Kim, Hee-Sun ; Yang, Kwang-Hee ; Kim, Cha-Soon ; Lim, Yong-Khi ; Kim, Chong-Soon ; Woon, Jae-Ho ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 9~15
Firstly, we compared the two staining techniques, Giemsa and Acridine orange, to determine micronuclei on samples of cultures of five healthy human peripheral blood lymphocytes after
in dose ranges of 0 to 800cGy. It was found that the Acridine orange staining method gives more reliable results than the usual Giemsa staining method in micronucleus tests. Moreover, the frequency of micronuclei in cytokinesis-blocked human B-lymphocytes was studied after in vitro irradiation in dose ranges of 0 to 50cGy. After setting and separating the B-lymphocytes, the frequency of radiation-induced micronuclei were observed as the end-point markers for the low-dose radiation dosimetry after staining with Giemsa and Acridine orange dyes. The micronuclei frequency in B-lymphocytes was significantly elevated from 10 to 30cGy
. The determination of micronuclei in B-lymphocytes after staining with Acridine orange was higher than that of Giemsa. The frequency of micronuclei in B-lymphocytes was observed to be at least two times higher than those of T-lymphocytes Giemsa in dose increasing. Therefore, the determination of low-dose radiation-induced micronuclei in B-lymphocytes after staining with Acridine orange is likely to have the greatest potential in the estimation of low dose radiation exposure.
Manufacture of a Gamma-ray Source using the Neutron Activation and Determination of a HPGe Detector Efficiency
Seo, Bum-Kyoung ; Lee, Kil-Yong ; Yoon, Yoon-Yeol ; Lee, Kune-Woo ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 17~23
In order to save time and money needed in the purchase commonly used gamma-ray standard sources, a new radioactive standard source was manufactured by the neutron activation of some regent in the research reactor HANARO. The source was manufactured with an aqueous solution by mixing and dissolving the irradiated reagents. The manufactured source was compared with a commercial standard source. It was confirmed that it could be used as an efficiency calibration source. Also, in order to compare the variation of efficiency due to the volume difference for various containers used in radioactivity assay, the efficiency variation as a function of sample volume was investigated.
A Study on the Spatial Resolution of Gas Detectors Based on EGS4 Calculations
Moon, B.S. ; Han, S.H. ; Kim, Y.K. ; Chung, C.E. ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 25~31
Results of EGS4 based calculations to study the spatial resolution of gas detectors are described. The calculations include radial distribution of electrons generated by photons of various energies penetrating into variable thickness of Ar and Xe gas layers. Given a desired spatial resolution, the maximum allowed thickness of gas layer for each energy level is determined. In order to obtain 0.1mm spatial resolution, the maximum thickness for the Ar gas is found to be 2mm for photon energies below 14keV while the optimum energy of photons for Xe gas with the same thickness is about 45keV. The results of calculations performed to compare the number of electrons generated by CsI coated micro-channel plate and the number of electrons generated by the Ar and Xe gas layers are described. The results show that the number of electrons generated by the gases is about 10 times higher than the one generated by CsI coated micro-channel plate. A few sample gray scale images generated by these calculations are included.
Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass
Kim, C.W. ; Choi, J.R. ; Ji, P.K. ; Park, J.K. ; Shin, S.W. ; Ha, J.H. ; Song, M.J. ; Hwang, T.W. ; Park, S.J. ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 33~39
In order to vitrify the W1 waste (ion-exchange resin(IER), zeolite, and dry active waste(DAW)) generated from Korean Nuclear Power Plants, a glass formulation development based on waste compositions and production rates was performed. A aluminoborosilicate glass, AG8W1, was formulated to vitrify the W1 waste in an induction cold crucible melter(CCM). The processability, product performance, and economics of the candidate glass were calculated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product quality of the glass such as chemical durability, phase stability, etc. was satisfactory. The vitrification process using the candidate glass was also evaluated to be operated as economically as possible.
Development of a Computer Code for Low-and Intermediate-Level Radioactive Waste Disposal Safety Assessment
Park, J.W. ; Kim, C.L. ; Lee, E.Y. ; Lee, Y.M. ; Kang, C.H. ; Zhou, W. ; Kozak, M.W. ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 41~48
A safety assessment code, called SAGE (Safety Assessment Groundwater Evaluation), has been developed to describe post-closure radionuclide releases and potential radiological doses for low- and intermediate-level radioactive waste (LILW) disposal in an engineered vault facility in Korea. The conceptual model implemented in the code is focused on the release of radionuclide from a gradually degrading engineered barrier system to an underlying unsaturated zone, thence to a saturated groundwater zone. The radionuclide transport equations are solved by spatially discretizing the disposal system into a series of compartments. Mass transfer between compartments is by diffusion/dispersion and advection. In all compartments, radionuclides ate decayed either as a single-member chain or as multi-member chains. The biosphere is represented as a set of steady-state, radionuclide-specific pathway dose conversion factors that are multiplied by the appropriate release rate from the far field for each pathway. The code has the capability to treat input parameters either deterministically or probabilistically. Parameter input is achieved through a user-friendly Graphical User Interface. An application is presented, which is compared against safety assessment results from the other computer codes, to benchmark the reliability of system-level conceptual modeling of the code.
A Reference Container Concept for Spent Fuel Disposal : Structural safety for dimensioning of the reference container
Choi, Jong-Won ; Kwon, Sang-Ki ; Kang, Chul-Hyung ; Kwon, Young-Joo ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 49~55
This paper presents the mechanical and thermal stress analysis of a disposal canister to provide basic information for dimensioning the canister and configuration of the canister components. The structural stress analysis is carried out using a finite element analysis code, NISA, and focused on the structural strength of the canister against the expected external pressures due to the swelling of the bentonite buffer and the hydrostatic head, and the thermal load build up in the container.
Review on the Working Hours of Radiation Work Plan for ECT through In-service Inspection
Chae, Gyung-Sun ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 57~63
As a part of In-service Inspection works in a nuclear power plant, Eddy Current Testing through all the outage of nuclear power plants has been controlled by the radiation management. From the case study about the periodical ECT work, the exposed dose rate of worker has announced over the organized dose rate before the radiation work, it affects the personnel exposed dose management and radiation work permit issue. It is not easy to get some information about ECT related working hours, scope of work and how many workers to forecast the radiation working and the predict dose exposure. It should be need the data accumulation about ECT related radiation work to prepare the ALARA achievement and the radiation work plan for dose mitigation. We can discuss a few information about ECT related radiation working issue for the application of predict dose exposure on this paper.
Application of Multi-Attribute Utility Analysis for the Decision Support of Countermeasures in Early Phase of a Nuclear Emergency
Hwang, Won-Tae ; Kim, Eun-Han ; Suh, Kyung-Suk ; Jeong, Hyo-Joon ; Han, Moon-Hee ; Lee, Chang-Woo ;
Journal of Radiation Protection and Research, volume 29, issue 1, 2004, Pages 65~71
A multi-attribute utility analysis was investigated as a tool for the decision support of countermeasures in early phase of a nuclear accident. The utility function of attributes was assumed to be the second order polynomial expressions, and the weighting constant of attributes was determined using a swing weighting method. Because the main objective of this study focuses on the applicability of a multi-attribute utility analysis as a tool for the decision support of countermeasures in early phase of a nuclear accident, less quantifiable attributes were not included due to lack of information. In postulated accidental scenarios for the application of the designed methodology, the variation of the numerical values of total utility for the considered actions, e.g. sheltering, evacuation and no action, was investigated according to the variation of attributes. As a result, it was shown that the numerical values of total utility for the actions are distinctly different depending on the exposure dose and monetary value of dose. As increasing in both attributes, the rank of the numerical values of total utility increased for evacuation, which is more extreme action than for sheltering, while that of no action decreased. As expected probability of high dose is higher, the break-even values for the monetary value of dose, which are the monetary value of dose when the ranking of actions is changed, were lower. In audition, as aversion psychology for dose is higher, the break-even values for dose were lower.