Valence control of charge and orbital frustrated system YbFeO with electrochemical Li intercalation

Murase, Satoshi*; Yoshikawa, Yumi*; Fujiwara, Kosuke*; Fukada, Yukimasa*; Teranishi, Takashi*; Kano, Jun*; Fujii, Tatsuo*; Inada, Yasuhiro*; Katayama, Misaki*; Yoshii, Kenji; et al.

Journal of Physics and Chemistry of Solids, 162, p.110468_1 - 110468_6, 2022/03

https://doi.org/10.1016/j.jpcs.2021.110468

We report a trial of the valence control for mixed valence iron triangular oxide YbFeO in order to develop an effective technique to control the frustration of charges in strongly correlated electron systems. The electro-chemical doping of Li into YbFeO was examined on the cell type sample similar to the Li-ion secondary battery cell. Systematic change of the lattice constant, Fe-Fe and Fe-Yb distance were observed with Li doping. Maximum value of the doping was over 300 mAh/g. An EXAFS experiment indicated that Li positioned between Yb octahedron layer (U-layer) and Fe-bipyramidal layer (W-layer). However, detailed change of iron valence state of YbFeO was not clearly observed because of the superimpose of the signal from iron metal nano particles in XANES observation. The results indicate that the electrochemical method might be one of the potential technique to control the frustration of charges in YbFeO.

Radiation monitoring using manned helicopter around the Fukushima Daiichi Nuclear Power Station in the fiscal year 2014 (Contract research)

Sanada, Yukihisa; Mori, Airi; Ishizaki, Azusa; Munakata, Masahiro; Nakayama, Shinichi; Nishizawa, Yukiyasu; Urabe, Yoshimi; Nakanishi, Chika; Yamada, Tsutomu; Ishida, Mutsushi; et al.

JAEA-Research 2015-006, 81 Pages, 2015/07

JAEA-Research-2015-006.pdf:22.96MB

By the nuclear disaster of Fukushima Daiichi Nuclear Power Station (NPS), Tokyo Electric Power Company (TEPCO), caused by the East Japan earthquake and the following tsunami occurred on March 11, 2011, a large amount of radioactive materials was released from the NPP. These results of the aerial radiation monitoring using the manned helicopter in the fiscal 2014 were summarized in the report.

Development of grouting technologies for HLW disposal in Japan, 5; Development and application of numerical model for grout injection process during in-situ grouting test

Koyama, Tomofumi*; Katayama, Tatsuo*; Tanaka, Tatsuya*; Kuzuha, Yuji; Onishi, Yuzo*

Proceedings of 7th Asian Rock Mechanics Symposium (ARMS-7) (USB Flash Drive), p.712 - 720, 2012/10

Grouting is commonly used to decrease the hydraulic conductivity of the fractured rock masses and control the groundwater inflow. Since underground facilities were constructed in various geological conditions, different types of grout material and mixing/injection methods were developed for effective and economical grout injection. It is also important to evaluate the grout arrival distance and the range of altered hydraulic conductivity field after grout injection. However, the mechanism of grout injection process has not been clarified sufficiently yet due to complicated chemical and physical processes of grout. In this study, to simulate the grout injection process, the three-dimensional numerical model based on equivalent continuum approach was developed and applied to the in-situ grout injection tests at Grimsel test site, Switzerland. In the simulations, the injection pressure and/or injection rate was given as a boundary condition and total amount of injected grout (silica sol) was calculated. The simulation results were also compared with the ones obtained from in-situ measurements/monitoring and show qualitatively good agreement.

Development of grouting technologies for geological disposal of high level waste in Japan, 3; Numerical simulation for grout injection using equivalent continuum model

Koyama, Tomofumi*; Katayama, Tatsuo*; Hasui, Akinori*; Tanaka, Tatsuya*; Kishi, Hirokazu; Onishi, Yuzo*

Dai-41-Kai Gamban Rikigaku Ni Kansuru Shimpojiumu Koenshu (CD-ROM), p.83 - 88, 2012/01

In this study, to simulate the grout injection process, the 3-D numerical model based on equivalent continuum approach was developed. The viscosity measurements for silica sol was performed to measure the time-dependent viscosity. The developed numerical model was applied to the planned in-situ grout injection tests at Grimsel test site (GTS), Switzerland. The rock type is fractured granite and the equivalent porous media was created from the DFN (Discrete Fracture Network) based on the frature data obtained from the observation boreholes. The preliminary simulation was carried out to determine the suitable grout injection pressure and investigate the arrival distance of grout from injection boreholes.

Recent progress in blanket materials development in the Broader Approach Activities

Nishitani, Takeo; Tanigawa, Hiroyasu; Nozawa, Takashi; Jitsukawa, Shiro; Nakamichi, Masaru; Hoshino, Tsuyoshi; Yamanishi, Toshihiko; Baluc, N.*; Mslang, A.*; Lindou, R.*; et al.

Journal of Nuclear Materials, 417(1-3), p.1331 - 1335, 2011/10

https://doi.org/10.1016/j.jnucmat.2010.12.304

As a part of the Broader Approach (BA) activities, the research and development on blanket related materials and tritium technology have been initiated toward DEMO by Japan and EU. Recently, those five R&D items have progressed substantially in Japan and EU. As a preparatory work aiming at the RAFM steel muss-production development, a 5-ton heat of RAFM steel (F82H) was procured with the Electro Slag Re-melting as a secondary melting. The result of the double notch tensile test method for the NITE-SiC/SiC specimen indicated notch insensitivity and very minor size effect on proportional limit tensile stress and fracture strength. For the fabrication technology development of beryllide neutron multiplayer pebbles, Be- Ti inter-metallic pebbles have been sintered directly from the mixed powder of Be and Ti in Japan.

Fusion materials development program in the Broader Approach activities

Nishitani, Takeo; Tanigawa, Hiroyasu; Jitsukawa, Shiro; Nozawa, Takashi; Hayashi, Kimio; Yamanishi, Toshihiko; Tsuchiya, Kunihiko; Mslang, A.*; Baluc, N.*; Pizzuto, A.*; et al.

Journal of Nuclear Materials, 386-388, p.405 - 410, 2009/04

https://doi.org/10.1016/j.jnucmat.2008.12.146

The establishment of the breeding blanket technology is one of the most important engineering issues on the DEMO development. For the DEMO blanket, developments of the structural materials and functional materials such as tritium breeder and neutron multiplier. Which should be used under the savior circumstance such as high neutron fluence, high temperature and strong magnetic field, are urgent issues. In the Broader Approach activities initiated by EU and Japan, developments of reduced activation ferritic martensitic steels as a DEMO blanket structural material, SiC/SiC composites, advanced tritium breeders and neutron multiplier for DEMO blankets, are planed as common interest issues of EU and Japan. This paper describes the overview of the development program.

Ion beam effects on electrical characteristics of proton conductive polymer

Nagata, Shinji*; Konishi, Yoshitada*; Tsuchiya, Bun*; To, Kentaro*; Yamamoto, Shunya; Takahiro, Katsumi*; Shikama, Tatsuo*

Nuclear Instruments and Methods in Physics Research B, 257(1-2), p.519 - 522, 2007/04

https://doi.org/10.1016/j.nimb.2007.01.111

Effects of MeV ion irradiation on electrical characteristics of perfluorosulphonic polymer membrane have been studied. The DC electrical conductivity in dry condition increased of three orders of magnitude as a consequence of irradiation with MeV region H and He ion irradiation at a fluence of 2 10 ions/cm. The optical absorption in the ultra-violet region increased in the ion irradiated membrane due to the formation of fluorocarbon and peroxy radicals. The ion irradiation may form fluorocarbon and peroxy compounds and improve the transport property of protons in the membrane.

High temperature Youngs modulus of a fine-grained nuclear graphite oxidized or prestressed to various levels

Eto, Motokuni; Oku, Tatsuo; Konishi, Takashi*

Carbon, 29(1), p.11 - 21, 1991/01

https://doi.org/10.1016/0008-6223(91)90089-2

no abstracts in English

Recommended practice for small punch(SP) testing of metallic materials; Draft

*; *; *; *; *; *; Oku, Tatsuo; Kodaira, Tsuneo; Fukaya, Kiyoshi; Nishi, Hiroshi; et al.

JAERI-M 88-172, 20 Pages, 1988/09

JAERI-M-88-172.pdf:0.64MB

no abstracts in English

Long-term assessment of transport of radioactive contaminant in the environment of Fukushima (F-TRACE Project), 5; River simulation using one dimensional code TODAM

Saito, Tatsuo; Kurikami, Hiroshi; Onishi, Yasuo*; Oda, Yoshihiro; Kitamura, Akihiro

no journal, , 

The radioactive Cs deposited on the surface of Fukushima prefecture from Fukushima Nuclear Power Plant explosion occurred in 2011 is significant issue and the prediction of its distribution and fate is indispensable for a number of reason including external and internal radiation exposure and impacts on agricultural environments and aquatic biota. Cs is well known to adsorb with clay rich soils, and therefore its transportation mechanism is mainly in the form of soil erosion on the land surface and sediment-sorbed contaminants transport in the water system such as rivers. The transportation of Cs due to the soil erosion is simulated by USLE based model and that due to the river is simulated by TODAM model using USLE based model results as input data. In this trial calculation, we used the Ukedo river as a model river and transportation of sediments and Cs from the dam to the river mouth was simulated.