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Motoshima, Takayuki*; Matsui, Hiroya; Kawakubo, Masahiro*; Kobayashi, Masato*; Ichimura, Tetsuhiro*; Sugita, Yutaka
Nihon Genshiryoku Gakkai-Shi ATOMO
, 64(3), p.163 - 167, 2022/03
no abstracts in English
Noro, Naoko; Scharmer, C.*; Kawakubo, Yoko; Sekine, Megumi; Okuda, Masahiro; Inoue, Naoko
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 10 Pages, 2021/08
In the amid of COVID-19 pandemic, Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) developed and conducted regional training course on physical protection of nuclear materials and facility (PP RTC) for Asian countries in October 19-30, 2020 as an online course. Maintaining the quality of in-person two-week training through online platforms was a big challenge. For effective learning, ISCN combined e-learning (self-study) and interactive learning (virtual classroom) for its online PP RTC, and engaged participants through group exercise via Zoom meeting. The paper will describe efforts of ISCN and SNL to develop the online curriculum of PP RTC and share lessons learned and good practices for course development and course implementation. The paper will also explore future application of online contents in nuclear security capacity building even after the pandemic.
Okuda, Masahiro; Van Dassen, L.*; Lock, B.*; Inoue, Naoko; Noro, Naoko; Kawakubo, Yoko; Sekine, Megumi
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 9 Pages, 2021/08
Inoue, Naoko; Noro, Naoko; Kawakubo, Yoko; Sekine, Megumi; Okuda, Masahiro; Hasegawa, Nobuhiko*; Naoi, Yosuke
Proceedings of INMM & ESARDA Joint Virtual Annual Meeting (Internet), 10 Pages, 2021/08
Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) celebrated its 10th anniversary in December 2020. One of its pillars is capacity building support mainly to Asian countries. 183 trainings were implemented with more than 4,600 participants since its establishment, however, the COVID-19 pandemic impacted in the implementation of the trainings. ISCN/JAEA has started to develop the online trainings since April 2020, and implemented two regional trainings, Physical Protection and State System of Accounting for and Control (SSAC) for IAEA Safeguards in October and November 2020, respectively. The efforts continue in further development of trainings/workshops, including the regional training on Additional Protocol for IAEA Safeguards Agreement Commodity Identification Training, and other two national workshops with foreign instructors. Online training can provide not only training opportunities for those who have difficulty in traveling for security and safety reasons including under the travel restriction by COVID-19 pandemic, but also could serve in making them more effective and efficient, especially by the combination with in-person trainings. The pandemic, as a result, accelerate ISCN/JAEA to develop and implement the online trainings, which key is the international collaboration with the partners including IAEA, DOE/NNSA and Sandia National Laboratories and International Nuclear Nonproliferation and Security Academy (INSA) of the Korea Institute of Nuclear Nonproliferation and Control (KINAC). This paper will provide the efforts of ISCN/JAEA how to address the online training development and implementation, current status, lesson learned, and future plan.
Tachikawa, Hirokazu*; Kawakubo, Fumie*; Shimizu, Akihiko*; Shibata, Toshio*; Sugimoto, Katsuhisa*; Seo, Masahiro*; Tsuru, Toru*; Fujimoto, Shinji*; Inoue, Hiroyuki*
JAEA-Research 2006-058, 80 Pages, 2006/10
JAEA-Research-2006-058.pdf:10.86MB
The Japan Nuclear Cycle Development Institute submitted "Second Progress Report on Research and Development for the Geological Disposal of HLW in Japan" to the Japanese government. This report contains investigations of the corrosion life time of the overpack on the basis of experimental data and past research, assuming the ranging geological environment of Japan. However some subjects, such as the behavior of the overpack under high pH conditions and the behavior of the engineering barrier with change of near-field environmental condition with time for promoting reliability have still been left. To take into account these conditions, expert committee composed of metal corrosion science experts were established in the Nuclear Safety Research Association and past research outcomes and the theory of safety assessment were investigated from the view points of long term stability and corrosion resistance of engineering barrier.
Nakayama, Mariko*; Kobayashi, Masato*; Kawakubo, Masahiro*; Suzuki, Kei*; Eto, Jiro*; Nakayama, Masashi; Ono, Hirokazu; Asano, Hidekazu*
no journal, ,
no abstracts in English
Takeuchi, Ryuji; Iwatsuki, Teruki; Takayasu, Kentaro; Kawakubo, Masahiro*; Kobayashi, Masato*
no journal, ,
no abstracts in English
Jo, Mayumi*; Iwatani, Takafumi*; Kawakubo, Masahiro*; Ishii, Tomoko*; Ono, Makoto*; Nakayama, Masashi
no journal, ,
For the purpose of "maintaining the soundness of the artificial barrier", we are studying "restraints on the outflow of the buffer material". We conducted an experiment of a scale of 30 cm to 1 m in an actual underground environment and confirmed the occurrence of the buffer material outflow under water inflow conditions. The experiment in this study was undertaken in order to acquire the necessary data for considering a method to control the outflow of the buffer material.
Yamazaki, Kazutoshi*; Takao, Hajime*; Kikuchi, Takahiro*; Kuriki, Yoshiro*; Kobayashi, Masato*; Kawakubo, Masahiro*; Shirase, Mitsuyasu*; Iwata, Yumiko*; Tochigi, Yoshikatsu*; Nakayama, Gen*; et al.
no journal, ,
Among factors affecting the corrosion behavior of carbon steel overpack, in order to consider materials (size) and realistic environmental factors which are difficult to reproduce in the laboratory scale test, engineering scale tests in the underground environment were carried out. A mock-up test of the same scale was also carried out on the ground with the aim of controlling and evaluating factors that govern the corrosion phenomenon. As a result of the test for about 3 years, there was no big difference between the average corrosion amount and the maximum corrosion amount of the simulated overpack base metal and the welded part. On the other hand, unlike the laboratory scale test, localization of corrosion due to the adhesion between the buffer material and the simulated overpack was also confirmed during the initial transient period.
Noro, Naoko; Kawakubo, Yoko; Sekine, Megumi; Okuda, Masahiro; Numata, Masaaki; Inoue, Naoko
no journal, ,
COVID-19 pandemic severely impacted capacity building support activities. Due to the travel restrictions, it became impossible to conduct in-person training for Asian participants, and domestic courses had to overcome various challenges as well. With the prolonged pandemic, it is essential to continue providing capacity building support in nuclear security field. The paper will share the experience of ISCN/JAEA on its capacity building support activities under COVID-19, and propose methods for capacity building support in the post COVID-19.
