REVIEW OF SAFEGUARDABILITY IN VIEW OF REGULATION

Under the NPT regime, nuclear non-proliferation is one of the key elements in evaluation of the nuclear fuel cycle facilities. International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) and Generation IV International Forum (GIF) listed elements to evaluate the future nuclear fuel cycle facilities, and proliferation resistance is one of the features. Developed evaluation tools through INPRO and GIF have been applied to evaluate model fuel cycle facilities with given scenarios. When it comes to select the future nuclear fuel cycle facilities, proliferation resistance is one of the most important factors. For example, when we compare the PUREX and Pyroprocessing, Pyroprocessing has advantage in proliferation resistance. Different from the definition of the safeguardability by the IAEA, Proliferation Resistance has two types of features: one is intrinsic and the other is extrinsic. Generally, during the selection/determination phase of the facility, which is conceptual design phase, intrinsic features affect dominantly the proliferation resistance. Design phase will come only after it is selected, therefore extrinsic features are overlooked. In fact, some features of intrinsic and extrinsic have negative affection each other. For example, separation of the Pu/U from other TRUs has negative value in intrinsic feature, but will be positive in accounting point of view. In this paper, we reviewed the elements of the safeguardability. We separated the elements in 4 categories: design information questionnaire, material accounting, verification and containment and surveillance. Measures of each category are listed as tables. These elements need to be considered according to its development phase of the nuclear fuel cycle. GIF defined the safeguardability as the degree of ease with which a nuclear energy system can be effectively and efficiently placed under international safeguards. It shows the efficiency as well as the effectiveness is important. This should be considered during the design phase. When we listed safeguardability related measures, we added values to the measures that can contribute to the efficiency. Through this research, we developed the basis to evaluate the safeguardability. Also it can be used in guiding the developer of the nuclear fuel cycle facility to establish safeguards system in timely manner.