[en] Space, including Earth, is filled with radiation. In any place, under any circumstances, the amount of radiation is extremely low, but it cannot be completely eliminated. Human beings are in a radiation environment because radiation exists in the entire environment that human beings are in contact with. I would like to describe the history of the environmental radioactivity survey in Korea. As a part of environmental monitoring activities, the results of the environmental radioactivity analysis conducted by each institution are published in the form of reports on the internet site. And the government plans to database all the environmental radiation data of Korea and will provide it to the general public

[en] For the study and verification of this technology, it is necessary to develop the experimental facility with hot cells and auxiliary systems in the future. In this paper, several safety analysis methodologies of Korea and the United States for the development of fuel cycle facilities are introduced, and the properties of the experimental pyroprocessing facility are practically analyzed using the associated safety analysis approaches. For developing safer pyroprocessing facilities it is necessary to analyze the basic properties of these safety analysis methodologies.

[en] Using the Nuclear Safety Act by the clearance and remediation of the site, decommissioning regulation, project performance and technical requirements, and criteria were derived. It is possible to supplement the decommissioning requirements management database of the nuclear facilities decommissioning information management system through the behavior diagram analysis and the user interface implementation to define the decommissioning activity requirements. This means that WBS, processes and references can be entered into the decommissioning requirements management database to supplement the decommissioning requirements management database of the nuclear decommissioning information management system.

[en] The purpose of this analysis is to identify the criticality margin for the metal storage cask. The metal storage cask assumed that 32 spent fuel assemblies could be stored and considered the worst conditions. The criticality evaluation was carried out applying burnup credit effect according to SFSTISG-8(Re.3). And the reduction of the reactivity according to the cooling period was also considered. Evaluation was performed to identify critical margins for the metal storage cask.

[en] This study tries to classify the existing development cases of servo-type telemanipulator systems in a nuclear area, and introduce the specification of the BDSM developed by KAERI for the performance comparison. This paper covers a comparison of telemanipulators which have different specifications of in their geometry, actuation type and control strategy as well as the comparison of their performances and specifications with the ones of BDSM system originally developed in KAERI. It is important, especially in nuclear facility when various kinds of customized telemanipulator systems have to be compared each other technically. Also, up-to-date telemanipulator systems and their innovative applications will be surveyed even the teleoperation systems in a nuclear area have a tendency to stick to the traditional approaches for safety and reliability

[en] The advanced spent fuel conditioning process facility (ACPF), which was constructed with air cell, was modified to consist of an air cell and an argon cell. The argon cell was constructed by isolating a part of the air cell, and argon gas is circulated. This paper describes a gastight door installed in preparation for situations such as installation of equipment and utilities during argon cell construction and emergency operation. The emergency door is designed with three link mechanism, so it can tightly push three surfaces.

[en] When spent fuels are placed in dry storage, hydrides from corrosion are dissolved and reprecipitated radially. Such radial hydrides can have a severe effect on mechanical properties of spent fuel at drop accident during transportation. In this report, we reviewed and analyzed the process of the predicting amount of radial hydrides. Only a small fraction of the hydrides reprecipitated radially in dry storage. As depicted in Fig. 3, less than 15 ppm of radial hydrides is expected after 40 years of dry storage. These model results will be used in integrity evaluation process to predict the mechanical properties of spent fuel rods

[en] Kori Unit 1 dismantling project has some anticipation of hardship due to unprecedented. Therefore different ways are needed from those of construction project in developing the schedule. Hence this paper proposes methods for generation of activity and the estimation of the working period, which are major concerns of the dismantling project schedule development. This paper introduces a method for schedule development of NPP dismantling project; integrated UCF, area division on the bases of work quantity, concept of activity generation, work period calculation methodologies, and major review points. By applying this approach, it is expected to improve the schedule reliability of the first dismantling NPP project of at Kori unit 1 in Korea

[en] A PADIRAC cask, RD 15, manufactured by La Calhène, is used in the ACPF hot-cell of KAERI. For the proper use and successful operation of the cask, a crane system is indispensable because it provides means to accurately adjust the position and orientation of the cask when connecting it to hot-cell door system. In this work, we propose a customized PADIRAC cask transport system used where no crane service is available near the docking position like ACPF hot-cell. In this work, we developed a customized shielded cask transport system which is equipped with a railguided travelling unit and a position adjustment unit for the cask without any crane service. The designed solid model was verified to have sufficient safety margin by using structural analysis.

[en] In order to evaluate the SNF cladding integrity during the transportation, knowing the loads at first, then the responses from the fuel itself is essential. Proposition for appropriate failure measures which would be used as failure criteria for the SNF cladding during the transportation with quantification is presented. It is important to set up a reasonable failure criterion for cladding, because being able to determine the cladding integrity during transportation is essential for the evaluation of SNF transportation system. There are a few of measures which can be used as a failure criterion for cladding subjected to its specific failure mode. In order to justify and quantify that criterion properly, various experiments for the mechanical properties of the claddings with different conditions shall be implemented, which data will enable to justify the failure criteria proposed