[en] The neutron fluxes and dose rates due to radiation streaming from reactor cavities were evaluated at the KNU-1 reactor pressure vessel(RPV) head flange elevation. To find a suitable cross section data set for the evaluation, a benchmark test was performed for three data sets; DLC-23/CASK, DLC-31/FEWG, and DLC-47/BUGLE. The leakage fluxes from the KNU-1 RPV outer surface were calculated with two different methods; 1-D calculation with ANISN, and 2-D calculation with DOT3.5. The Monte Carlo procedures as embodied in the MORSE-CG code combined with the albedo option were applied to predict the radiation distributions in the cavity region. Finally, the activation analysis of the stud bolts was performed to identify the major activation products. (Author)

[en] The International Commission on Radiological Protection (ICRP) has established Task Group 94 (TG 94) to develop a publication on the ethical foundations of the system of radiological protection aiming to consolidate the basis of ICRP's recommendations, to improve the understanding of the system and to provide a basis for communication on radiation risk and its perception. Through the review of the publications of the Commission and the conduct of a series of workshops, TG 94 has identified the key components of the ethical theories and principles relevant to the system of radiological protection. The purpose of eliciting the ethical values underpinning the system of radiological protection is not only to clarify the rationale of the recommendations made by the Commission, but also to assist in discussions related to its practical implementation. The report nearing completion by TG 94 will present the key steps concerning the scientific, ethical and practical evolutions of the system of radiological protection since the first ICRP publication in 1928, describe the core ethical values underpinning the present system and address the key procedural aspects for its implementation. (authors)

[en] Recently, rapid progress on the globalization of the nuclear safety issues is being made in IAEA (International Atomic Energy Agency) and its member states. With the globalization, the need for international cooperation among international bodies and member states continues to grow for resolving these universal nuclear safety issues. Furthermore, the importance of strengthening the global nuclear safety regime is emphasized through various means, such as efforts in application of IAEA safety standards to all nuclear installations in the world and in strengthening the code of conduct and the convention on nuclear safety. In this regards, it is important for us to keep up with the activities related with the global nuclear safety regime as an IAEA member state and a leading country in nuclear safety regulation

[en] Full text: International Commission on Radiological Protection (ICRP) is about to publish new recommendations on radiation protection. International Atomic Energy Agency (IAEA) is also under process in revising its International Basic Safety Standards (BSS) to take into account of the changes of the ICRP recommendations. As soon as the revision of the BSS is completed, Korean government is considering to implement those changes in the BSS and the ICRP recommendations into its national radiation protection laws and regulations. This paper introduces the current activities and future prospects in this matter. In the 2007 ICRP recommendations, there are some new concepts, principles and quantities such as the changes in the nominal risk coefficient for cancer and hereditary effects, new definitions on the tissue weighting factors and radiation weighting factors for neutron and proton, extended application of the dose constraints in all exposure situations in source-related radiation protection, and the introduction of new system of protection for non-human species. Based on the study carried out by KINS so far, the following points are identified as major areas that need for further in-depth review and consideration for the implementation of the ICRP 2007 recommendations into Korean radiation protection laws and regulations; changes in the radiation risk factors, radiation weighting factors and tissue weighting factors, maintenance of the ICRP 60 dose limits, practical application of the dose constraints and determination of the reference levels in many source to individual exposure relationships, change from process-based system to exposure situation-based system, strengthening of the principle of optimization in all exposure situations, system of radiation protection for the environment, practical application of the exclusion and exemption principles, active participation of the stake holders, changes in glossary etc. The study for the implementation of the ICRP 2007 recommendations into national legislations will be conducted until the end of 2012. In the meantime, draft regulations will be developed and the possible impact on the nuclear industry will also be analyzed and active involvement of the stake holders including licensees will be encouraged in the entire process of implementation of the ICRP 2007 recommendations into Korean radiation protection laws and regulations. The final draft of the revised laws and regulations will be issued in the early of 2013 and the formal legislation process of this final draft will commence in due course. (author)

[en] Since it first was operated in 1988, the facility of radioactive waste management installation in National Nuclear Energy Agency (BATAN) Indonesia has many radioactive waste packages in cementation form 1070 of drums 200 liters, 148 of concrete shell 950 liters and 10 of wooden box which is contain with contaminated scrap metal. The procedure for representative sampling and analysis waste was developed. According to the analysis result, Cs-137 and Co-60 were major radionuclide while some of wastes were contaminated with Th-234, Ra-226, and U-238 with an extremely low concentration. Based on IAEA GSR Part 3, the analysis result shows that radioactive wastes in concrete shell have activity concentration of Cs-137 and Co-60 far as below 0.1 Bq/g. The contaminated scrap metal also have radioactivity α contamination as below 0.37 Bq/cm2. It was estimate individual dose as below 10 μSv/years. This assessment can be applied as suggestion for improving on National Energy Regulatory Agency (BAPETEN) regulatory regarding clearance level of the scrap metal and concrete shell at radioactive waste management in Indonesia.

[en] In 2007, the International Commission on Radiological Protection (ICRP) revised, updated, consolidated, and developed Recommendations of the International Commission on Radiological Protection (ICRP 103). Accordingly IAEA safety standards committees (RASCC, WASSC, NUSSC and TRANSSC) have reviewed and revised the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (BSS 1996). The reasons and objectives for proceeding to a revision of the BSS are as follows: · Link a revised BSS to the new Safety Fundamentals and to take account of new ICRP recommendations, · To take account of more recent international agreements such as conducts, codes, guidance and conventions, · To ensure consistency with and appropriate cross referencing to closely related publications, · For improvements that could be made to the text of the BSS on clarity, detail and consistency. To maximize the merit of revision, it is essential that careful attention should be paid by member states. During last few years, there have been many meetings relating to the revision of the BSS, including drafting meetings, technical meetings, and coordination meetings. From these meetings the revised BSS (draft 1.0, draft 2.0, draft 2.5, and draft 3.0) were made

[en] Recently a high-quality voxel model of a Korean adult male was constructed at Hanyang University by using very high resolution serially-sectioned anatomical images of a cadaver, which was provided by the Korean Institute of Science and Technology Information (KISTI). Most existing voxel phantoms are developed based on an individual in the supine posture. This study converted the HDRK-Man voxel model into surface model and adjusted the flattened back of the HDRK-Man to a normal shape in the upright posture using 3D graphic software such as 3D-DOCTOR^TM, Rapidform 2006, Rhinoceros 4.0, MAYA 8.5. The effective doses of adjusted model were compared with those of unadjusted model for some standard irradiation geometries (i.e., AP, PA, LLAT, RLAT). In general, the differences were not very large and, among those, the largest difference was found for the PA radiation geometry, as expected. These methodologies can be used for the development of various deformed posture models of HDRK-Man in the later stage of this project

[en] Currently, many countries have plans to increase their nuclear energy use in several areas, especially in electric power generation. Those countries include not only the developed countries such as, U.S.A., Russia, U.K., Canada but also the developing counties like China, India, Vietnam, Indonesia, Nigeria and so on. The worldwide trend to increase nuclear energy use is due to recent rapid increase in energy demand for economic growth, Kyoto Protocol and the advance in nuclear technologies resulting in enhancement of the safety level and the performance of NPPs. In this situation, the international nuclear community is continuously making effort to ensure and to improve the global nuclear safety through Conventions (Convention on Nuclear Safety and etc.), the development and application of international safety standards and the international cooperation. Among these efforts for global nuclear safety, recent activities in INRA (International Nuclear Regulators' Association) and in MDEP (Multinational Design Evaluation Program), which have caught attention from many countries, will be introduced in this paper

[en] This study was conducted to measure the uranium concentrations in urine of some members of the general public in Busan and Daejeon and to assess the annual committed effective doses from uranium analysis of daily excretion. As a result, the ranges of total uranium concentrations in the urine for the residents in Busan and Daejeon were found to be 0.556 - 1.53 mBg L^-1 and 2.18 - 4.55 mBg L^-1, respectively. It was noted that the uranium concentrations for the residents in Daejeon were observed to be higher than those for the residents in Busan. This result assumes that the uranium concentrations in the urines for the residents in Daejeon are probably related to the high uranium concentrations contained in the drinking water of Daejeon city. The bedrock of Daejeon, known as granitic rocks formed in the Jurassic period of the Mesozoic Era, contains high uranium contents. Also, results showed no significant correlation with age or sex. The ranges of annual committed effective doses from ingestion of uranium for the residents in Busan and Daejeon were calculated to be 0.472-1.41 μSν and 1.99-4.15 μSν, respectively

[en] The INRA (International Nuclear Regulators' Association) was established as an association of top regulators in 1997 to influence and enhance nuclear safety and radiological protection from the regulatory perspective. The members include the most senior officials of well-established independent national nuclear regulatory organizations. Previously, it had 9 members from 8 member countries; U.S. (NRC), France (ASN), Sweden (SKI), U.K. (NII), Canada (CNSC), Germany (BMU), Spain (CSN) and Japan (NSC and NISA). As of March 2006, the Director General for Atomic Energy Bureau in MEST of Korea became the 10^th member of the INRA. From this time, Korea has participated in the INRA regular meetings and shared its knowledge and experience in nuclear safety regulation area with members