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Sekio, Yoshihiro; Yoshimochi, Hiroshi; Kosaka, Ichiro; Hirano, Hiroyasu; Koyama, Tomozo; Kawamura, Hiroshi
Proceedings of 52nd Annual Meeting of Hot Laboratories and Remote Handling Working Group (HOTLAB 2015) (Internet), 8 Pages, 2015/09
Due to the Fukushima Daiichi Nuclear Power Plant accident in March 2011, the safe and secure implementations of the decommissioning for Fukushima Daiichi Nuclear Power Plant has been positioned as the urgent tasks in Japan. Japan Atomic Energy Agency has a critical mission of analysing radioactive wastes having generated by the accident for long-term storage and disposal methods. This will be performed in two hot laboratories to be constructed in Okuma Analysis and Research Center at Fukushima Daiichi Nuclear Power Plant site. In one laboratory, radioactive wastes such as rubbles and secondary wastes will be treated, whereas debris such as fuel debris and high dose structural materials will be handled in the other laboratory. The detail considerations for advanced techniques and experimental apparatus to be installed are underway.
Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki*; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
Journal of Power and Energy Systems (Internet), 4(1), p.244 - 251, 2010/04
no abstracts in English
Kitagaki, Toru; Tasaka, Masayuki; Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
Proceedings of 17th International Conference on Nuclear Engineering (ICONE-17) (CD-ROM), 5 Pages, 2009/06
JAEA has been developing a reliable disassembly system for FBR fuel reprocessing as a part of Fast Reactor Cycle Technology Development (FaCT). We fabricated the disassembly system testing machine. In this paper, we described design of it.
Hirano, Hiroyasu
Saikuru Kiko Giho, (23), 0 Pages, 2004/00
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.
; Hirano, Hiroyasu; Koyama, Tomozo
OECD/NEA 7th information exchange meeting, 0 Pages, 2002/00
None
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PNC TJ8409 91-001, 146 Pages, 1991/03
Based on literatures collected by PNC, technical informations of TRUEX process has been surveyed. In order to make clear whether the informations necessary for the process evaluation are avairable or not, informaitons obtained from the literatures are arranged and combined for future R&D planing. This report describes a present status of TRUEX process development in the US and Italy, the data on physical properties of TRUEX solvent, and extraction-separation behaviors of TRU, FP and inactive elements have been arranged and filed for the process evaluation. Merits and demerits of the TRUEX process have been compared with those of two other processes (DIDPA : JAERI and Malonamides : CENFAR) Which have the same objectives as that of the TRUEX process. Further, R&D plans necessary for the conformation of applicability and for the realisation of this process have been proposed.
; Hirano, Hiroyasu; ; Tanaka, Yasumasa; Kawata, Tomio
International Conference on Envilonmental of Fuel, ,
None
Hirano, Hiroyasu; Nomura, Kazunori; ; ; ;
International Information Exchange Programe on Actinide & Fission Product Separation & Transmutation, ,
None
Hirano, Hiroyasu; ; ; Nomura, Kazunori; ;
International Information Exchange Programe on Actinide & Fission Product Separation & Transmutation, ,
None
Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Kitagaki, Toru; Washiya, Tadahiro; Kobayashi, Tsuguyuki*; Tasaka, Masayuki*
no journal, ,
no abstracts in English
Kitagaki, Toru; Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Tasaka, Masayuki*; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
no journal, ,
no abstracts in English
Nagai, Takayuki; Kikuchi, Kotaro*; Hirano, Hiroyasu; Fukasawa, Kazuhito*; Uehara, Akihiro*; Yamana, Hajimu*
no journal, ,
In the dry reprocessing process for spent nuclear fuel by the electro-metallurgical method, we are studying the online monitoring technique of dissolved ion concentration in molten LiCl-KCl eutectic. In this study, the cyclic voltammetry was carried out in the molten LiCl-KCl eutectic added lanthanide chlorides (NdCl
, etc.) and we confirmed that the peak current density by the reductive reaction of dissolved ions increased in proportion to the dissolved ion concentration until about 4 mol%.
Fukushima, Mineo; Nagai, Takayuki; Kikuchi, Kotaro*; Hirano, Hiroyasu; Myochin, Munetaka
no journal, ,
Measurement techniques for density and liquid level of molten salt are very important elements in material accountancy system for pyro-processing and also in process control system. Test equipments were developed for the in-situ measurement of density and liquid level of molten salt and provided to the measurement experiments. Measurement of the density of LiCl-KCl eutectic showed a good agreement with published data in an error of 0.2%. Measurement of the liquid level of LiCl-KCl eutectic showed an error of 0.5 mm against theoretical values. From these results, both techniques were considered to be promising although the additional data accumulation is needed to estimate the performance statistically by using practical equipment.
Nagai, Takayuki; Uehara, Akihiro*; Fukazawa, Kazuhito*; Fujii, Toshiyuki*; Hirano, Hiroyasu; Yamana, Hajimu*
no journal, ,
no abstracts in English
Arai, Yoichi; Fujisaku, Kazuhiko*; Koizumi, Satoshi*; Ogino, Hideki; Hirano, Hiroyasu
no journal, ,
no abstracts in English
Koma, Yoshikazu; Shibata, Atsuhiro; Nakahara, Masaumi; Ogino, Hideki; Arai, Yoichi; Onishi, Hiroyuki*; Nakajima, Yasuo; Hirano, Hiroyasu; Washiya, Tadahiro
no journal, ,
Concerning reprocessing technology for spent FBR fuel, the results of development on solvent extraction for co-recovery of U, Pu and Np will be reviewed. Chemical processing simplified by considering the condition that moderate decontamination is allowed and centrifugal contactor that provides better plant operating ratio and less Pu inventory were developed.
Ito, Rintaro; Suzuki, Kenta; Horiuchi, Kazunori; Hirano, Hiroyasu
no journal, ,
In the decommissioning of TEPCO Fukushima Daiichi Nuclear Power Plant (1F), it is important to prepare in advance based on data and information on the spatial structure and dose distribution within the facility is important. The virtual reality system (VR system) of the Naraha Remote Technology Development Center presents the structure and equipment of 1F in 3D and can also present the dose distribution. This system is utilized for planning, training, etc. of the work related to decommissioning. In order to make effective use of this VR system in the future, it is also required to reproduce precisely the situation at the work site, to enable planning and training, etc of work in the situation close to the workplace. To that end, it will be necessary to expand 1F data to be incorporated into the VR system and to quickly reflect on-site situations that are constantly changing due to work. In this paper, we report on attempts to enhance the functions of the VR system that we recently worked on, taking into account such points.
Shibata, Atsuhiro; Yano, Kimihiko; Sambommatsu, Yuji; Nakahara, Masaumi; Takeuchi, Masayuki; Hirano, Hiroyasu; Nakajima, Yasuo; Washiya, Tadahiro
no journal, ,
no abstracts in English
Higuchi, Hidetoshi; Koizumi, Kenji; Hirano, Hiroyasu; Kitagaki, Toru; Takeuchi, Masayuki; Washiya, Tadahiro; Kobayashi, Tsuguyuki*
no journal, ,
no abstracts in English
