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Sr in cattle bone and tooth samples by inductively coupled plasma mass spectrometryKoarai, Kazuma; Matsueda, Makoto; Aoki, Jo; Yanagisawa, Kayo*; Terashima, Motoki; Fujiwara, Kenso; Kino, Yasushi*; Oka, Toshitaka; Takahashi, Atsushi*; Suzuki, Toshihiko*; et al.
Journal of Analytical Atomic Spectrometry, 36(8), p.1678 - 1682, 2021/08
Times Cited Count：5 Percentile：55.72(Chemistry, Analytical)Rapid analysis of Sr in bone and tooth samples of cattle were achieved by an inductively coupled plasma mass spectrometry (ICP-MS) coupled with mass shift and solid phase extraction techniques. Limit of detection (LOD) in the ICP-MS measurement of 0.1 g samples was lower than that of the radioactivity measurement. Analytical time of the ICP-MS method was reduced from 20 days to 11 hours, compared with the radiometric method. Therefore, the ICP-MS method can be rapid and useful procedure of Sr in small bone and tooth samples derived from terrestrial animals.
Tamai, Hiroshi; Mochiji, Toshiro; Senzaki, Masao*; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Dai-41-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2020/11
In light of recent delay of plutonium use in Japan and the increasing criticism of nuclear non-proliferation and nuclear security in the nuclear fuel cycle, the validity of these criticisms will be examined for the sustainable development of the nuclear fuel cycle policy. Issues on the view point of nuclear non-proliferation and nuclear security are examined.
Mochiji, Toshiro; Senzaki, Masao*; Tamai, Hiroshi; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Enerugi Rebyu, 40(8), p.56 - 57, 2020/07
Strict application of IAEA safeguards and nuclear security should be implemented for Japan's full-scale nuclear fuel cycle. Based on the knowledge and experience of research and development in the nuclear fuel cycle, nuclear material management, the effective and efficient promotion of new technologies should be promoted with scientific and demonstrative measures to strengthen the world's nuclear non-proliferation and nuclear security. Development or sophistication of new technologies, human resource development, and reinforcement of the international framework are future challenge in the international community.
Mochiji, Toshiro; Senzaki, Masao*; Tamai, Hiroshi; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Enerugi Rebyu, 40(7), p.58 - 59, 2020/06
Japan have promoted the peaceful use of plutonium with the nuclear non-proliferation commitment based on IAEA safeguards agreement and Japan-US nuclear cooperation agreement, as well as ensuring transparency of the policy that Japan has no plutonium without purpose of use. In promoting the nuclear fuel cycle, adherence to those measures and maintaining plutonium utilization by means of plutonium-thermal, and a fast reactor cycle to achieve large-scale and long-term energy supply and environmental improvement, therefore, further research and development is essential.
Mochiji, Toshiro; Senzaki, Masao*; Tamai, Hiroshi; Iwamoto, Tomonori*; Ishiguro, Yuzuru*; Kitade, Yuta; Sato, Heigo*; Suehiro, Rie*; Taniguchi, Tomihiro*; Fukasawa, Tetsuo*; et al.
Enerugi Rebyu, 40(6), p.58 - 59, 2020/05
In order to promote the peaceful use of nuclear energy, it is important not only to ensure safety but also to ensure nuclear non-proliferation and nuclear security. Japan has contributed to the international community through strengthening nuclear non-proliferation and nuclear security capabilities with technical and human resource development. However, in the wake of the accident at the Fukushima Daiichi Nuclear Power Plant in 2011, Japan's nuclear power plants have not restarted or plutonium use has not progressed smoothly. Concerns have been shown. Towards appropriate steps of Japan's nuclear fuel cycle policy, such concerns are examined and future efforts are summarized.
Morishita, Yoshitsugu; Yanagisawa, Tsutomu*
Wagakuni Shorai Sedai No Enerugi O Ninau Kakunenryo Saikuru; Datsu Tanso Shakai No Enerugi Anzen Hosho; NSA/Commentaries, No.24, p.119 - 126, 2019/03
no abstracts in English
Yanagisawa, Tsutomu*; Usami, Shin; Maeda, Seiichiro
Genshiryoku Nenkan 2018, p.90 - 95, 2017/10
no abstracts in English
Sato, Koji; Yanagisawa, Tsutomu*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 56(4), p.271 - 276, 2014/04
This article introduces the trend of nuclear power development of India, in which the current energy and electric power situation, the nuclear energy policy (historical background, nuclear development organization, three-stage nuclear power development program, introduction plan of electric power and nuclear power, and interantional cooperation), current status of nuclear development (first phase: thermal neutron reactors (pressurized heavy-water reactors (PHWR) and light water reactors (LWR)) and related fuel cycle, secondary stage: fast reactors and related fuel cycle, third stage: advanced reactors and related fuel cycle, development of human resources, influence of the TEPCO's Fukushima Dai-ichi Nuclear Power Station accident, and the expectation for nuclear cooperation are described.
Yamaguchi, Akira*; Yanagisawa, Tsutomu; Moriyama, Hirotake*
Nihon Genshiryoku Gakkai-Shi ATOMO, 52(10), p.626 - 637, 2010/10
This article introduces the innovative technologies that examine the adoption to the sodium-cooled fast reactor as an approach for commercial use of the fast reactor cycle system, as the final of serial, mainly by International Conference (FR09) organized by IAEA and held in December, 2009. The latest situation of the research and development and the simulation technology concerning a reactor technologies such as the reactor configuration, the reactor system design, and the cooling system devices are reviewed. Fuel development, wet reprocessing and pyro-reprocessing technologies are also reviewed by the views for the future. In addition, the problem of safety, a nuclear nonproliferation, an operating experience, a technological transfer between generation, and the human resource is described, including the expectation to Japan by the utilization of Monju and Joyo.
Yanagisawa, Tsutomu; Tabata, Hiroaki; Mori, Masaomi
E-Journal of Advanced Maintenance (Internet), 2(1), 7 Pages, 2010/05
Monju, the Japanese prototype of fast breeder reactor, has engaged in various activities to restore the public trust since the sodium leak accident occurred in 1995. Among the activities is the publication of a risk communication booklet "Response to the possible accident and trouble in Monju" which is compiled according to the operational progress of "Monju". This booklet is intended for promoting the public understanding toward the restart. The supplement of the booklet illustrates the outline and characteristics of "Monju", the recent troubles at not only "Monju", but also home and abroad, and the assumed troubles during the core confirmation test which is implemented when the system start-up test is commenced. These efforts for the restart are also explained.
Yanagisawa, Tsutomu; Tabata, Hiroaki; Mori, Masaomi
Hozengaku, 8(3), p.17 - 22, 2009/10
Monju, the Japanese prototype of fast breeder reactor, has engaged in various activities to restore the public trust since the sodium leak accident occurred in 1995. Among the activities is the publication of a risk communication booklet Response to the Possible Accident and Trouble in Monju which is compiled according to the operational progress of Monju. This booklet is intended for promoting the public understanding toward the restart. The supplement of the booklet illustrates the outline and characteristics of Monju, the recent troubles at not only Monju, but also home and abroad, and the assumed troubles during the Core Confirmation Test which is implemented when the System Start-Up Test is commenced. These efforts for the restart are also explained.
Hayashi, Hideyuki; Yanagisawa, Tsutomu
Nihon Genshiryoku Gakkai-Shi ATOMO, 49(8), p.556 - 564, 2007/08
The outline of the concept changes of fast reactor designs from the beginning to the present are described, while the current leading concept is sodium cooled MOX fueled. As for the reactor core, the reason of selecting the coolant and the fuel material is mentioned concerning reactor physics and thermal design, such as heat removal capability and material characteristics. As for the reactor structure, the difference between loop type and tank type is mentioned citing past reactor designs and current Japanese design for commercialization.
Yanagisawa, Tsutomu; Tanabe, Hiromi
Nihon Genshiryoku Gakkai-Shi ATOMO, 49(7), p.499 - 504, 2007/07
The first story of this serial handles the early days of FBRs. The progress of nuclear physics in the 1930's led to the development of the FBR. Fast neutrons as for fission generator, plutonium for nuclear fuels and liquid metal as for the coolant were selected to obtain a higher breeding ratio. Based on the experience of the Clementine Reactor, the EBR-I went critical in August 1951. Moreover, they succeeded in electricity generation in December 1951 and later confirmed breeding. The results of EBR-I project are thought to demonstrate the controllability of the fast neutron, the utility of liquid metals, and the reality of breeding.
Yanagisawa, Tsutomu;
Fukui University, 0 Pages, 2004/10
Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.
Miyakawa, Shunichi; Yanagisawa, Tsutomu; ; ; Mitsugi, Takeshi
P247, 247 Pages, 2002/00
None
Chatani, Keiji; Yanagisawa, Tsutomu;
International Scientific-Practieal Confenence XXI; Nuclear Weapon Free Century, 0 Pages, 2001/00
None
; Takahashi, Katsuro; Yanagisawa, Tsutomu
Nuclear Technology, 118, p.14 - 25, 1998/00
Times Cited Count：21 Percentile：82.17(Nuclear Science & Technology)None
Yanagisawa, Tsutomu
Nihon Genshiryoku Gakkai-Shi, 37(2), p.112 - 123, 1995/02
Times Cited Count：3 Percentile：36.75(Nuclear Science & Technology)