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Suzuki, Hideya; Tsubata, Yasuhiro; Kurosawa, Tatsuya; Shibata, Mitsunobu; Kawasaki, Tomohiro; Urabe, Shunichi*; Matsumura, Tatsuro
Analytical Sciences, 32(4), p.477 - 479, 2016/04
Times Cited Count：24 Percentile：68.53(Chemistry, Analytical)An impeccable, high-performance new reagent called alkyl diamide amine (ADAAM) was examined from the viewpoint of mutual separation of Am(III) and Eu(III). ADAAM has three donor atoms, one soft N-donor atom and two hard O-donor atoms, in the central frame. The combination of soft and hard atoms affords a tridentate donor set of atoms that ensures remarkable extractability and selectivity of Am(III) and Eu(III) in highly acidic media.
Fukaya, Masaaki*; Noda, Masaru*; Hata, Koji*; Takeda, Yoshinori*; Akiyoshi, Kenji*; Ishizeki, Yoshikazu*; Kaneda, Tsutomu*; Sato, Shin*; Shibata, Chihoko*; Ueda, Tadashi*; et al.
JAEA-Technology 2014-019, 495 Pages, 2014/08
JAEA-Technology-2014-019.pdf:82.23MB
The researches on engineering technology in the Mizunami Underground Research Laboratory (MIU) plan consists of (1) research on engineering technology deep underground, and (2) research on engineering technology as a basis of geological disposal. The former research is mainly aimed in this study, which is categorized in (a) development of design and construction planning technologies, (b) development of construction technologies, (c) development of countermeasure technologies, and (d) development of technologies for security. In this study, the researches on engineering technology are being conducted in these four categories by using data measured during construction as a part of the second phase of the MIU plan.
Magome, Hirokatsu; Okada, Yuji; Hanawa, Hiroshi; Sakuta, Yoshiyuki; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Shibata, Mitsunobu
JAEA-Technology 2014-023, 267 Pages, 2014/07
JAEA-Technology-2014-023-01.pdf:103.68MBJAEA-Technology-2014-023-02.pdf:71.92MB
In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from 2012 to 2014 in the follow-up report reported before (JAEA-Technology 2013-019).
Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Omi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu
JAEA-Technology 2013-019, 236 Pages, 2013/10
JAEA-Technology-2013-019.pdf:45.07MB
In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year.
Yamaguchi, Tetsuji; Negishi, Kumi; Ebashi, Katsuhiro; Inagaki, Shingo*; Shibata, Mitsunobu*; Tanaka, Tadao; Nakayama, Shinichi
JAERI-Conf 2004-011, p.139 - 140, 2004/07
Uncertainties should be quantitatively assessed in a long-term assessment of radioactive waste disposal. We focus our experimental efforts on parameters that induce major uncertainties in the radionuclide migration analysis and that have not been quantitatively understood. Solubility of radionuclides, diffusion in bentonite buffer material and sorption on rocks were investigated to quantify the uncertainties associated with the parameters and to minimize the uncertainties.
Matsumura, Tatsuro; Tsubata, Yasuhiro; Urabe, Shunichi; Shibata, Mitsunobu; Ichimura, Seiji; Hagiya, Hiromichi*; Tsujimoto, Kazufumi
no journal, ,
no abstracts in English
Suzuki, Hideya; Tsubata, Yasuhiro; Urabe, Shunichi; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Matsumura, Tatsuro
no journal, ,
JAEA continues to carry out the development of the ADS(Double-strata). Mutual separation of MA and Ln is important for the development of the partitioning process. The separation is particularly difficult, because they have the analogous chemical behavior. New reagent was synthesized and examined. The results of separation factors (SF) of Am against Eu are more than 25. The reagent is very stable chemically, high extraction capacity, fully miscible with hydrocarbon diluents, fast chemical kinetics, and following the CHON-principle.
Urabe, Shunichi; Tsubata, Yasuhiro; Suzuki, Hideya; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Matsumura, Tatsuro
no journal, ,
JAEA continues to carry out the development of the ADS (Double-strata). Mutual separation of MA and Ln is important for the development of the partitioning process. TDdDGA was performed using a mixer-settler equipment for the development of the separation process for MA. TDdDGA has a high extraction capacity. TDdDGA consists of C, H, O and N atoms (the CHON-principle). In this experiment, the feed solution as simulated HLLW contained fourteen elements. The results of the counter-current test showed that Am was extracted and was recovered in a high yield.
Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi; Matsumura, Tatsuro
no journal, ,
JAEA continues to carry out the development of the ADS(Double-strata). Mutual separation of MA and Ln is important for the development of the partitioning process. The separation is particularly difficult, because they have the analogous chemical behavior. New reagent was synthesized and examined. The results of separation factors (SF) of Am against Eu are more than 25, SFAm/Cm = 5.5. The reagent is very stable chemically, high extraction capacity, fully miscible with hydrocarbon diluents, fast chemical kinetics, and following the CHON-principle.
Matsumura, Tatsuro; Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi
no journal, ,
no abstracts in English
Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi; Matsumura, Tatsuro
no journal, ,
JAEA continues to carry out the development of the ADS(Double-strata). Mutual separation of Am(III) and Cm(III) is important for the development of the partitioning process. The separation is particularly difficult, because they have the analogous chemical behavior. Alkyl diamide amine (ADAAM), a new high-performance reagent with a simple structure, was examined for the mutual separation of Am(III) and Cu(III). The combination of ADAAM and N,N,N',N'-tetraethyldiglycolamide (TEDGA) as a masking agent shows selectivity for Am(III) over Cm(III) in highly acidic media with separation factors up to 41.
Matsumura, Tatsuro; Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi
no journal, ,
no abstracts in English
Suzuki, Hideya; Sasaki, Yuji; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi; Matsumura, Tatsuro
no journal, ,
Hexaalkyl-nitrilotriacetamide (NTAamide) was evaluated for the separation of MA(III) and RE(III). NTAamide is a multidentate ligand comprising one soft N-donor atom and three hard O-donor atoms as part of its central frame. This tetradentate set of donor atoms provide selective binding for Am(III) and Nd(III) and yield separation factors of up to 3.7. A continuous liquid liquid extraction and stripping process were performed using Hexaoctyl-NTAamide (HONTA) in n-dodecane as the extractant in a multistage countercurrent mixer-settler extractor. Separation of MA(III) and RE(III) in high yield was demonstrated.
Suzuki, Hideya; Yamashita, Kiyoto*; Murayama, Rin*; Ban, Yasutoshi; Shibata, Mitsunobu; Kurosawa, Tatsuya*; Kawasaki, Tomohiro; Sagawa, Hiroshi*; Sasaki, Yuji; Matsumura, Tatsuro
no journal, ,
Hexaalkyl-nitrilotriacetamide (NTAamide) was evaluated for the separation of MA(III) and RE(III). NTAamide is a tetradentate ligand with one soft central N-donor atom and three hard carbonyl O-donor atoms in its skeleton. NTAamide was tested for the removal of MA(III) and RE(III) from HNO
into n-dodecane. MA(III) and RE(III) separation was demonstrated with a high yield through the extraction process using NTAamide. This study shows that NTAamide is a highly practical, high-performance extractant for partitioning MA(III) from RE(III).
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Toigawa, Tomohiro; Kurosawa, Tatsuya*; Shibata, Mitsunobu*; et al.
no journal, ,
To continue the utilization of the nuclear fission energy, the management of the high-level radioactive waste is one of the most important issues to be solved. Partitioning and Transmutation technology is expected to be effective to mitigate the burden of the HLW disposal by reducing the radiological toxicity and heat generation. JAEA has been conducting R&D on the MA separation process to remove of MA from HLW and supply the recovered MA to the transmutation system such as ADS. The MA separation process contains three steps. For An(III)+RE recovery process, we developed TDdDGA which has very high performance to recover of MA from high level waste. HONTA and ADAAM were developed for An(III)/RE separation process and Am/Cm separation process respectively. All extractants satisfy CHON principle to minimization of the secondary waste from the process. The separation performances of the flowsheets were evaluated by continuous extraction tests using simulated and genuine high level liquid waste.
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Toigawa, Tomohiro; Kurosawa, Tatsuya*; Shibata, Mitsunobu*; et al.
no journal, ,
PUREX process was established for industrial scale reprocessing plant. TRUEX and the 4 group separation were developed for partitioning of minor actinides from HLW, and demonstrated using genuine HLW. Although the extractants for the processes have excellent performance, the molecules contain phosphorus which could be cause for the secondary waste from the solvent extraction processes. To minimize the radioactive waste, we have conducted research and development of the new reprocessing and MA separation processes using innovative extractants in accord with CHON principle. The extractants for reprocessing process are monoamides as alternative extractants for TBP. For An(III)+RE recovery process, we developed TDdDGA. HONTA and ADAAM were developed for An(III)/RE separation process and Am/Cm separation process respectively. The separation performances of the flowsheets were evaluated by continuous extraction tests using simulated and genuine spent fuel and high level liquid waste.
Suzuki, Hideya; Tsubata, Yasuhiro; Ban, Yasutoshi; Shibata, Mitsunobu*; Kurosawa, Tatsuya*; Kawasaki, Tomohiro*; Matsumura, Tatsuro
no journal, ,
The authors have developed a new extractant for the separation of minor actinide (MA) from high-level liquid waste (HLLW). Tetra-2-ethylhexyldiglycolamide (TEHDGA) has four branched alkyl chains and has high solubility in diluents. Furthermore, TEHDGA has high selectivity of MA from fission products, high extraction capacity, fast extraction kinetics, fast phase separation, and low cost. TEHDGA is a highly practical extractant for partitioning MA from HLLW.
Matsumura, Tatsuro; Ban, Yasutoshi; Suzuki, Hideya; Tsubata, Yasuhiro; Hotoku, Shinobu; Tsutsui, Nao; Suzuki, Asuka; Toigawa, Tomohiro; Kurosawa, Tatsuya*; Shibata, Mitsunobu*; et al.
no journal, ,
PUREX process was established for industrial scale reprocessing plant. TRUEX and the 4 group separation were developed for partitioning of minor actinides from high level liquid waste from reprocessing process, and demonstrated by the continuous extraction test using genuine high level liquid waste. Although the extractants for reprocessing and MA separation processes, such as tri-n-butyl phosphate (TBP), n-octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide (CMPO) and diisodecylphosphoric acid (DIDPA), have excellent performance for recovery of U, Pu or MA, the molecules contain phosphorus which could be cause for the secondary waste from the solvent extraction processes. To minimize the radioactive waste from nuclear fuel cycle, we have conducted research and development of the new reprocessing and MA separation processes using innovative extractants in accord with CHON principle.
Suzuki, Hideya; Tsubata, Yasuhiro; Kurosawa, Tatsuya*; Kawasaki, Tomohiro*; Shibata, Mitsunobu*; Matsumura, Tatsuro
no journal, ,
The authors have developed new extractants for the separation of minor actinide (MA) from high-level liquid waste. Tetra-2-ethyldecyldiglycolamide (TEDDGA) has four branched alkyl chains and high selectivity of MA from fission products. Furthermore, TEDDGA has high solubility in diluents, high extraction capacity, and fast phase separation.
Suzuki, Hideya; Tsubata, Yasuhiro; Kurosawa, Tatsuya*; Kawasaki, Tomohiro*; Shibata, Mitsunobu*; Matsumura, Tatsuro
no journal, ,
The Japan Atomic Energy Agency is engaged in research and development of the "SELECT process" which is a separation technology for recovering actinides from spent fuel. A highly practical reagent, called HONTA, was developed. In the present study, HONTA was tested for the mutual separation of MA and RE.
