• Journal of Radiation Protection and Research
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• v.30 no.3
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• pp.149-159
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• 2005

The purpose of this paper is to present the general attributes of the current IAEA programs and their prospects in the arena of protection of the marine and terrestrial environment, thus responding to a need to attain a consolidated understanding of the Agency's programs for an effective and efficient deployment of the respective national R&D projects in Korea. In addition, the considerable and beneficial benefits from a participation in the IAEA programs have been analyzed and their immediate relevance has been emphasized. A strategy for the enhancement of an active participation in the program and its efficient implementation has also been established. It is expected that the suggested recommendations such as the long term strategy and the relevant guidelines will be helpful in establishing a nuclear policy for the further development of the international cooperative projects in the future.

• Journal of Radiation Protection and Research
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• v.30 no.4
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• pp.247-252
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• 2005

The main idea of this paper is to present the general attributes of the current IAEA programs and their prospects in the arena of occupational radiation protection, thus responding to a need to attain a consolidated understanding of the Agency's programs for an effective and efficient deployment of the respective national R&D projects in Korea. In addition, the considerable and beneficial benefits from a participation in the IAEA programs have been analyzed and their immediate relevance has been emphasized. A strategy for the enhancement of an active participation in the program and its efficient implementation has also been established. It is expected that the suggested recommendations such as the long term strategy and the relevant guidelines will be helpful in establishing a nuclear policy for the further development of the international cooperative projects in the future.

• Nuclear Engineering and Technology
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• v.56 no.7
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• pp.2698-2703
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• 2024

A bilateral comparison was conducted between the International Atomic Energy Agency (IAEA) and the Korea Research Institute of Standards and Science (KRISS) to measure the absorbed dose to water in accelerator photon beams. KRISS served as a linking laboratory to compare the IAEA standard with the key comparison reference value (KCRV) of the BIPM.RI(I)-K6 program, in which KRISS participated in 2017. Two ionization chambers from the IAEA were used as transfer instruments for the comparison. Both laboratories measured the calibration coefficients of these instruments and calculated the ratios. The ratio of the KRISS standard to the KCRV was applied to obtain the degree of equivalence of the IAEA, along with its uncertainty. The largest deviation of the IAEA measurement from the KCRV was 3.4 mGy/Gy, significantly smaller than the expanded uncertainty of 10.7 mGy/Gy (k = 2, 95% level of confidence). This study demonstrates the equivalence of IAEA's measurement standard for accelerator photon beams to other primary standard dosimetry laboratories. It provides evidence for the satisfactory operation of IAEA's quality management system and enhances the international credibility of the IAEA SSDL network, particularly in high-energy accelerator photon beams from linear accelerators.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.22 no.1
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• pp.45-54
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• 2024

Currently, off-site dose calculations for nuclear power plants are conducted using a computer program (K-DOSE 60). The program is developed based on the regulatory guidelines of the Korea Institute of Nuclear Safety (KINS), which is a domestic nuclear regulatory agency. In this study, a domestic application of the International Atomic Energy Agency (IAEA) TRS (Technical Reports Series)-472 methodology for ³H and ¹⁴C in liquid effluents was studied. The dose-evaluation methods adopted and the program configuration for dose evaluation are described based on ³H and ¹⁴C in the liquid-effluent-evaluation module of the computer program. The accuracy of the program is verified by comparing the program-calculated results with hand calculation values. Furthermore, a comparative evaluation with LADTAP II, which is a liquid-effluent-evaluation methodology developed by the U.S. NRC (Nuclear Regulatory Commission), is performed. The result confirms that the program-calculated results for the IAEA TRS-472 methodology are consistent with the hand calculation values. Meanwhile, the result of comparative evaluation with LADTAP II indicates different results depending on the methodology used.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.121-121
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• 2004

As one of the major activities of the International Atomic Energy Agency (IAEA), a Coordinated Research Program (CRP) has been implemented with the aim of solving many of the problems facing the Member States by integrating various different levels of each country's technical capabilities in the areas which the Agency needs further technology development. To establish the strategy for an active participation In the CRP and its effective implementation, general features of the current IAEA programs and a prospect of the future program for 2006-2007 are described.(omitted)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11a
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• pp.221-228
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• 2005

The objectives of this paper are to present the general features of the current IAEA programs and their future prospects in the fields of the nuclear fuel cycle and the related materials technologies thus responding to a need to achieve a consolidated understanding of the Agency's programs for an effect ive implementation of the respective national R&D projects in Korea. During the development of the Agency's programs for 2005-2007 in the aforementioned fields. it is foreseen that an considerable attention will be attributed to the concepts, models and opportunities for optimizing the fuel cycle, mining the raw materials, re-using the materials and reducing the waste arisings (e.g. through Partitioning and transmutation), all of which, will Include an enhanced consideration for proliferation and security concerns.

• Journal of radiological science and technology
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• v.28 no.2
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• pp.79-89
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• 2005

This paper presents the overall attributes of the current IAEA programs and their future prospects in the arena of applications of radioisotopes and ionizing radiation, thus dealing with the demand to achieve a condensed understanding of the Agency's programs for an effective and efficient deployment of the respective national R&D projects in Korea. The considerable and beneficial advantages of a participation in the IAEA programs have been reviewed and their immediate relevance has been emphasized. A strategic approach for the enhancement of an active participation in the program and its efficient implementation has also been established. It is anticipated that the proposed recommendations such as the long term strategy and the applicable guidelines will be useful in formulating a nuclear policy for the further development of the international cooperative projects in the future.

• Journal of Radiation Protection and Research
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• v.27 no.2
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• pp.111-120
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• 2002

A reference scenario of vault safety case prepared by the IAEA for the near-surface disposal facility of low-and informed]ate-level radioactive wastes is assessed with the MASCOT program. The appropriate conceptual models for the MASCOT implementation is developed. An assessment of groundwater pathway through a drinking well as a geosphere-biosphere interface is performed first. then biosphere pathway is analysed to estimate the radiological consequences of the disposed radionuclides based on compartment modeling approach. The validity of conceptual modeling for the reference scenario is investigated where possible comparing to the results generated by the other assessment. The result of this study shows that the typical conceptual model for groundwater pathway represented by the compartment model ran be satisfactorily used for safety assessment of the entire disposal system in a cons]stent way. It is also shown that safety assessment of a disposal facility considering complex and various pathways would be possible by the MASCOT program.

• Radiation Oncology Journal
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• v.20 no.4
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• pp.381-390
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• 2002

Purpose : To develop a dose calibration program for the IAEA TRS-277 and AAPM TG-21, based on the air kerma calibration factor (or the cavity-gas calibration factor), as well as for the IAEA TRS-398 and the AAPM TG-51, based on the absorbed dose to water calibration factor, so as to avoid the unwanted error associated with these calculation procedures. Materials and Methods : Currently, the most widely used dosimetry Protocols of high energy photon beams are the air kerma calibration factor based on the IAEA TRS-277 and the AAPM TG-21. However, this has somewhat complex formalism and limitations for the improvement of the accuracy due to uncertainties of the physical quantities. Recently, the IAEA and the AAPM published the absorbed dose to water calibration factor based, on the IAEA TRS-398 and the AAPM TG-51. The formalism and physical parameters were strictly applied to these four dose calibration programs. The tables and graphs of physical data and the information for ion chambers were numericalized for their incorporation into a database. These programs were developed user to be friendly, with the Visual $C^{++}$ language for their ease of use in a Windows environment according to the recommendation of each protocols. Results : The dose calibration programs for the high energy photon beams, developed for the four protocols, allow the input of informations about a dosimetry system, the characteristics of the beam quality, the measurement conditions and dosimetry results, to enable the minimization of any inter-user variations and errors, during the calculation procedure. Also, it was possible to compare the absorbed dose to water data of the four different protocols at a single reference points. Conclusion : Since this program expressed information in numerical and data-based forms for the physical parameter tables, graphs and of the ion chambers, the error associated with the procedures and different user could be solved. It was possible to analyze and compare the major difference for each dosimetry protocol, since the program was designed to be user friendly and to accurately calculate the correction factors and absorbed dose. It is expected that accurate dose calculations in high energy photon beams can be made by the users for selecting and performing the appropriate dosimetry protocol.

• Food Industry And Nutrition
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• v.10 no.1
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• pp.48-53
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• 2005