Proliferation resistance and safeguardability of very high temperature reactor

Shiba, Tomooki; Tomikawa, Hirofumi; Hori, Masato

Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 6 Pages, 2018/11

Feasibility study result of advanced solution measurement and monitoring technology for reprocessing facility

Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi*; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A.*; Browne, M.*

Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 8 Pages, 2018/11

The IAEA has proposed, in its Research and Development plan (STR-385), the development of technology to enable real-time flow measurement of nuclear material as part of an advanced approach to effective and efficient safeguards for reprocessing facilities. To address this, JAEA and JNFL had previously designed and developed a neutron coincidence based non-destructive assay system to monitor Pu in solution directly after a purification process. To enhance this technology for entire reprocessing facilities, as a feasibility study, JAEA has been tackling development of a new detector to enable monitoring of Pu in solutions with numerous fission products (FPs) as a joint research program with the U.S. DOE. In this study, the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant (TRP) was used as the test bed. The design information of the HALW storage tank and radiation (type and intensity) were investigated, to develop a Monte Carlo N-Particle Transport Code (MCNP) model. Then, dose rate distribution inside the concrete cell where the HALW tank is located was measured, to enable design of new detectors and check the integrity of the MCNP model and its applicability. Using the newly-designed detectors, -rays and neutrons could be measured continuously at the outside/inside of the concrete cell, to optimize detector position and the radiation characteristics. The applicability as a Pu-monitoring technology was evaluated, based on the simulation results and -ray/neutron measurement results. We have found that there is a possibility to monitor the change of Pu amount in solution by combination of -ray and neutron measurements. The results of this study suggest a feasibility study into the applicability and capability of Pu monitoring to enhance the entire reprocessing facility handling Pu with FPs. In this paper, a summary of the project will be presented.

Virtual reality; ISCN's effective capacity-building tool

Rodriguez, P.; Suzuki, Mitsutoshi; Hanai, Tasuku

no journal, , 

Capacity-building is an important area, to be continually reinforced in order to maintain the successful operation of an entity or organization. The depletion of capable human resources due to retirement, ill-health and other unavoidable conditions should be addressed. Valuable knowledge and experience should be shared in a certain way; with ease of comprehension and information retention. Virtual reality (VR) is one tool that can be used in response to the urgent need to capture knowledge and experience from relevant resources. In 2016, the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) invested in virtual reality knowledge management technology to equip its Center of Excellence. The ISCN has developed a VR system that provides a three-dimensional computer-generated training environment, which can be explored and interacted with by an individual. Through this VR system, the participant becomes part of a virtual world, immersed within the environment. While there, the individual is able to manipulate objects or perform a series of actions. This paper describes how virtual reality is being used by the ISCN as an effective capacity-building tool. It will also describe the approach to how the knowledge and experience for a specific subject matter are conveyed through the use of virtual reality. The effectiveness of the tool has been demonstrated since its introduction through application on several occasions within the training course for the State System of Accounting for and Control of Nuclear Material (SSAC). Use of the VR tool brings benefits from zero exposure to radiation within a suitable environment for the participants' training, whilst enabling the learning of safeguards concepts and associated nuclear material verification measures.