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Barucci, M. A.*; Reess, J.-M.*; Bernardi, P.*; Doressoundiram, A.*; Fornasier, S.*; Le Du, M.*; Iwata, Takahiro*; Nakagawa, Hiromu*; Nakamura, Tomoki*; Andr
, Y.*; et al.
Earth, Planets and Space (Internet), 73(1), p.211_1 - 211_28, 2021/12
Times Cited Count：13 Percentile：80.63(Geosciences, Multidisciplinary)The MMX InfraRed Spectrometer (MIRS) is an imaging spectrometer on board of MMX JAXA mission. MIRS is built at LESIA-Paris Observatory in collaboration with four other French laboratories, collaboration and financial support of CNES and close collaboration with JAXA and MELCO. The instrument is designed to fully accomplish MMX's scientific and measurement objectives. MIRS will remotely provide near-infrared spectral maps of Phobos and Deimos containing compositional diagnostic spectral features that will be used to analyze the surface composition and to support the sampling site selection. MIRS will also study Mars atmosphere, in particular to spatial and temporal changes such as clouds, dust and water vapor.
Tsuji, Tomoyuki; Sugitsue, Noritake; Sato, Fuminori; Matsushima, Ryotatsu; Kataoka, Shoji; Okada, Shota; Sasaki, Toshiki; Inoue, Junya
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(11), p.658 - 663, 2020/11
no abstracts in English
Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki
QST-M-16; QST Takasaki Annual Report 2017, P. 60, 2019/03
Hydrogen gas generation by 
-radiation from cement solidified products loading low-level radioactive liquid waste generated at LWTF in Tokai Reprocessing Facility was studied.
Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*
Proceedings of 3rd International Symposium on Cement-based Materials for Nuclear Wastes (NUWCEM 2018) (USB Flash Drive), 4 Pages, 2018/10
At TRP, LWTF was constructed as a facility for processing low radioactive liquid waste and solid waste generated at TRP, and a cold test is been carrying out. In this facility, initially, nitrate waste liquid after separation of nuclides generated with treatment of low radioactive liquid waste was to be solidified by using borate. However, at present, it is necessary to decompose the nitrate in the liquid waste to reduce the environmental burden. For the reason, as a plan to replace the nitrate with the carbonate and to make it as a cement based encapsulation, we are studying for the introduction of the facility. Currently, as a cement solidification technology development for this liquid waste, we are studying the application of cement material based on blast furnace slag (BFS) as a main component. In this report, we show the results of the test conducted on the actual scale (200 L drum can scale).
Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori
QST-M-8; QST Takasaki Annual Report 2016, P. 69, 2018/03
no abstracts in English
Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu
QST-M-8; QST Takasaki Annual Report 2016, P. 62, 2018/03
no abstracts in English
Ito, Yoshiyuki; Sato, Fuminori; Kojima, Junji
QST-M-2; QST Takasaki Annual Report 2015, P. 89, 2017/03
no abstracts in English
Nakano, Takafumi; Sato, Fuminori; Shirozu, Hidetomo; Nakanishi, Ryuji; Fukuda, Kazuhito; Tachibana, Ikuya
Nihon Genshiryoku Gakkai-Shi ATOMO, 57(1), p.14 - 20, 2015/01
no abstracts in English
Sato, Fuminori; Terunuma, Hitoshi*; Arai, Osamu*; Myochin, Munetaka
Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(1), p.83 - 94, 2009/03
Oxide conversion using water vapor and boron oxide (B
O
) was studied to treat salt waste from dry reprocessing. Parameter tests to CsCl and NaCl-2CsCl salt were performed and fundamental data such as conversion rate, etc. were acquired. To understand the process behavior, a reaction analysis based on thermodynamic equilibrium calculation considering salt (NaCl, CsCl), oxide (NaO, CsO, BO) and gas (HO, Ar, HCl, NaCl, CsCl) phase was performed. The validity of analysis was confirmed by comparison with the experiment. Using this result, process condition of the oxide conversion (ex. temperature, added amount of HO and BO, etc.) was discussed.
Sato, Fuminori; Nakamura, Hirofumi
Proceedings of 2008 International Congress on Advances in Nuclear Power Plants (ICAPP '08) (CD-ROM), p.2046 - 2050, 2008/06
Kofuji, Hirohide; Sato, Fuminori; Myochin, Munetaka; Nakanishi, Shigeyuki*; Kormilitsyn, M. V.*; Ishunin, V.*; Bychkov, A. V.*
Journal of Nuclear Science and Technology, 44(3), p.349 - 353, 2007/03
Times Cited Count：7 Percentile：47.34(Nuclear Science & Technology)The Oxide Electrowinning method has being studied as one of the candidate dry reprocessing concepts of future fuel cycle system. On the MOX co-deposition process, main process of that method, some fundamental experiments have been performed to confirm its feasibility. In the experiments, several parameters were set to study the suitable electrolysis condition to obtain desired granule of MOX. The concentrations of uranium, plutonium, FP simulators, and CP simulators were adopted as the parameters. The blowing gas composition during the electrolysis was also set as the variable condition. Through these experiments, it was clarified that the partial pressure of chlorine gas during electrolysis was important to obtain MOX granule with high Pu concentration without generating bottom precipitation in melt. Finally, adequacy of process control method for MOX co-electrolysis was confirmed through the test using spent FR fuel.
Sato, Fuminori; Mizuguchi, Koji; Nakanishi, Shigeyuki; Myochin, Munetaka
Nihon Genshiryoku Gakkai Wabun Rombunshi, 5(4), p.268 - 281, 2006/12
MOX co-deposition process, which is one of the main parts of oxide electrowinning process, was studied by both sides of examination and analysis. Parameter tests using U and Pu were performed as basic examination, and fundamental data of the process such as polarization property of molten salt including U and Pu, current efficiency of electrolysis and PuO concentration in recovered deposit, etc. were acquired. In addition, to analyze the process behavior, especially polarization property at electrolysis, a reaction model considering Pu
, Pu
, UO
, UO
, PuO and PuOin molten NaCl-2CsCl salt was developed. The validity of this model was confirmed by comparison of the experimental and analytical results. Using this model behavior of chemical species in the process was studied and control factors of MOX co-deposition process were discussed.
Sato, Fuminori; Myochin, Munetaka; Terunuma, Hitoshi*; Arai, Osamu*
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 4 Pages, 2005/10
Oxide conversion of molten salt wastes in pyrochemical reprocessing was studied as a pre-treatment of vitrification. A new method using boron oxide and water vapor was suggested from consideration of a conventional method using boric acid (H3BO3) by chemical equilibrium calculation. Applying the new method for NaCl-CsCl salt in a small-scale experiment, it was confirmed that the most of the salt was converted to oxide and the amount of the oxide wastes after the treatment could be reduced by 20% compared with the conventional method.
Kobayashi, Tsuguyuki; Vavilov, S.; Sato, Fuminori; Myochin, Munetaka; Namba, Takashi*; Namba, T.*
Journal of Nuclear Science and Technology, 42(3), p.295 - 300, 2005/00
Times Cited Count：10 Percentile：56.74(Nuclear Science & Technology)The concept of air transport of A Type package containing nuclear fuel materials according to the nuclear disaster countermeasures law, and the experience of a transportation of plutonium solution from France are shown.
Sato, Fuminori; Myochin, Munetaka; Terunuma, Hitoshi*; Arai, Osamu*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(3), p.307 - 311, 2004/00
Out-of-pile experiments on the release of fission products (FPs) under transient heating conditions were carried out for mixed oxide fuels. The fuels used in the experiments, the plutonium content of which was 30wt%, were irradiated up to 65 GWd/t in the experimental fast reactor JOYO. The experiments consisted of two runs, FP-1 and FP-2. In FP-1, the fuel sample was first heated to 2,000
C and then up to 3,000C. The holding time was 30 min at each temperature. In FP-2, the terminal temperatures were 1,500C and 2,500C, and the holding time was 30 min in the same manner. The release of Cs, a volatile FP, was detected as soon as the fuel sample was heated up. The release rate, after peaking in several minutes, decreased gradually via a diffusion process in the fuel matrix. The "gross" diffusion coefficient agreed well with the data reported in other experiments using LWR fuels. The release fractions were identical in both experiments, namely Cs 100%, Sb 100%, Ru 10%, Ce 0% and Eu 0%.
Sato, Fuminori; Fukushima, Mineo; Myochin, Munetaka; Namba, Takashi
Proceedings of 11th International IUPAC Conference on High Temperature Materials Chemistry (HTMC-11), P. 210, 2003/00
None
*; Fujii, Toshiyuki*; Moriyama, Hirotake*; ; ; Myochin, Munetaka; Ojima, Hisao
JNC TY8400 2002-013, 57 Pages, 2002/03
JNC-TY8400-2002-013.pdf:32.32MB
no abstracts in English
; Sato, Fuminori; ; Mizuguchi, Koji*; Omori, Takashi*; Fujita, Reiko*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(3), p.312 - 316, 2002/00
None
Sato, Fuminori; Myochin, Munetaka
PS-8, 0 Pages, 2001/00
None
