[en] This paper presents JAEA-ISCN research and development programs for basic demonstration of 3 advanced NDA technologies of nuclear material in nuclear security and nuclear safeguards. Here we explain about contents of research and development of each NDA technology and present situation of each program. We also show possible applications of each NDA technology in nuclear security and safeguards. (author)

[en] The R and D for tritium technologies to a demonstration reactor (DEMO) are planned to be carried out in the Broader Approach (BA) program in Japan by JAEA with Japanese universities: (1) tritium analysis technology; (2) basic tritium safety research; and (3) tritium durability test. The EU joins the discussions and assessment of the R and D results. As the recent activities on the tritium technologies of the BA program, a multi-purpose RI facility, where the above R and D subjects will be carried out, has been designed in detail. A preliminary safety study has also been carried out for the amount of tritium released to the environment and for the radiation dose of workers. The facility is now under construction at Rokkasho in Aomori. The main subjects of the R and D of tritium analysis are the technologies for real-time analysis for hydrogen isotopes, gas, liquid and solid (such as microGC and calorimeter). The materials of interest include F82H, SiC, ZrCo, solid and liquid advanced breeder and multipliers. In the tritium durability tests, organic materials and metals planned to be used in a DEMO plant are studied for the radiation and the corrosion damage. A series of preliminary studies for the above subjects has been started.

[en] Upon its establishment in accordance with Japan’s commitment statement at the 2010 Nuclear Security Summit in Washington DC, the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) was missioned to provide support to efforts to strengthen nuclear security regimes internationally and nationally. Although capacity building support for safeguards has proven to be useful in ISCN’s experience, some nuclear security-specific features need to be considered regarding its application to nuclear security. These features include the self-determining nature of nuclear security requirements, the importance of nuclear security culture for its performance, and the involvement of professionals from a variety of backgrounds. These features have added a new perspective to ISCN’s approach to its nuclear security capacity building support. The paper presents this approach and what lessons can be drawn for its advancement. It begins with a description of challenges to nuclear security capacity building support, introduces ISCN’s experience in addressing these challenges, and discusses how to apply lessons learned to advance our nuclear security capacity building support. (author)

[en] This GUM WorkbenchTM propagation of uncertainty is for the coulometric measurement of the plutonium concentration in a Pu standard material (C126) supplied as individual aliquots that were prepared by mass. The C126 solution had been prepared and as aliquoted as standard material. Samples are aliquoted into glass vials and heated to dryness for distribution as dried nitrate. The individual plutonium aliquots were not separated chemically or otherwise purified prior to measurement by coulometry in the F/H Laboratory. Hydrogen peroxide was used for valence adjustment.

[en] The R and D effort on partitioning of minor actinides (MA) at the Japan Atomic Energy Agency (JAEA) has been concentrated on development and improvement of innovative extractants and adsorbents as the fundamental studies and of MA recovery process as the advanced aqueous reprocessing system in fast reactor cycle technology development (FaCT) project. This paper reviews current status and prospects of the R and D activities on the partitioning of MA at JAEA. (authors)

[en] This paper considers the experience of the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) in building up a qualified workforce in the area of safeguards. It starts explaining the long and thorough experience accumulated by JAEA’s former institutions and the reasons and mandate for the creation of ISCN under the JAEA. Then it describes some steps that preceded the establishment of the Center that provided the conceptual and practical basis of its activities. Some of ISCN’s most notorious accomplishments since its creation, including pertinent statistics and information are then explained. This paper also describes ISCN’s recent efforts in preparing and conducting regional surveys on training needs and training providers. These surveys provide a needs analysis, identify potential gaps in the provision of training, and assist training providers to optimize their use of existing training capabilities to meet those needs, hence assuring that safeguards training activities satisfy the actual needs of Asian countries and therefore they help to build up a qualified safeguards workforce. (author)

No abstract available

[en] We have constructed a new system which could analyze a position distribution of several elements in a sample with 2 dimensional prompt γ-ray analysis (2D PGA) system using focused neutron beam at JAEA. We aimed that the system could analyze local information in a sample with a good signal γ-ray from interested elements to noise of background γ-ray ratio. As a result, this system could determine the position resolution and spatial resolution within 1 mm. (author)

[en] Conclusion: • Requirements for ISF is currently under development by JAEA, SNL, KINAC and KAERI. • Requirements seek to help implement information sharing following PDCA cycle. • Requirements development is still underway, but expected to be finalized in near future. • Demonstration of ISF will be implemented as the next step. • ISF is expected to facilitate FR avoiding regional NP/NS concerns in a sustainable manner

[en] Japan Atomic Energy Agency (JAEA) has been developing the crystallization process technology in cooperation with Mitsubishi Materials Corporation, Saitama University and Waseda University. We have carried out experimental studies with uranium, MOX and spent fuel dissolved solution, and flowsheet analysis was researched. Crystal refinement study has been started to get more purified crystal. In association with these studies, an innovative continuous crystallizer and its system was developed to ensure high process performance. From the design study, an annular type continuous crystallizer was selected as the most promising design, and performance was confirmed by small-scale test and engineering scale demonstration at uranium crystallization conditions. In this paper, the research and development of crystallization process are described. (authors)