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JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2022

Kokubun, Yuji; Nakada, Akira; Seya, Natsumi; Nagaoka, Mika; Koike, Yuko; Kubota, Tomohiro; Hirao, Moe; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; et al.

JAEA-Review 2023-052, 118 Pages, 2024/03

JAEA-Review-2023-052.pdf:3.67MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2022. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2021

Nakada, Akira; Kanai, Katsuta; Kokubun, Yuji; Nagaoka, Mika; Koike, Yuko; Yamada, Ryohei*; Kubota, Tomohiro; Hirao, Moe; Yoshii, Hideki*; Otani, Kazunori*; et al.

JAEA-Review 2022-079, 116 Pages, 2023/03

JAEA-Review-2022-079.pdf:2.77MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2021. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2020

Nakano, Masanao; Nakada, Akira; Kanai, Katsuta; Nagaoka, Mika; Koike, Yuko; Yamada, Ryohei; Kubota, Tomohiro; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; et al.

JAEA-Review 2021-040, 118 Pages, 2021/12

JAEA-Review-2021-040.pdf:2.48MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2020. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2019

Nakano, Masanao; Fujii, Tomoko; Nagaoka, Mika; Koike, Yuko; Yamada, Ryohei; Kubota, Tomohiro; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Kikuchi, Masaaki*; et al.

JAEA-Review 2020-070, 120 Pages, 2021/02

JAEA-Review-2020-070.pdf:2.47MB

Based on the regulations (the safety regulation of Tokai Reprocessing Plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and by law of Ibaraki Prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2019. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

Journal Articles

Extraction of trivalent rare earths and minor actinides from nitric acid with ${it N,N,N',N'}$-tetradodecyldiglycolamide (TDdDGA) by using mixer-settler extractors in a hot cell

Ban, Yasutoshi; Suzuki, Hideya; Hotoku, Shinobu; Kawasaki, Tomohiro*; Sagawa, Hiroshi*; Tsutsui, Nao; Matsumura, Tatsuro

Solvent Extraction and Ion Exchange, 37(1), p.27 - 37, 2019/00

 Times Cited Count:21 Percentile:65.06(Chemistry, Multidisciplinary)

A continuous counter-current experiment using TDdDGA was performed using mixer-settler extractors installed in a hot cell. Nitric acid containing minor actinides (MAs: Am and Cm), rare earths (REs: Y, La, Nd, and Eu), and other fission products (Sr, Cs, Zr, Mo, Ru, Rh, and Pd) was fed to the extractor. TDdDGA effectively extracted MAs and REs from the feed, while other fission products were barely extracted. The extracted MAs and REs were back-extracted by bringing them in contact with 0.02 mol/dm$$^{3}$$ nitric acid, and they were collected as the MA-RE fraction. The proportions of MA and RE in the MA-RE fraction were $$>$$ 98% and $$>$$ 86%, respectively. These results demonstrated the applicability of TDdDGA as an extractant for MAs and REs.

Journal Articles

Highly practical and simple ligand for separation of Am(III) and Eu(III) from highly acidic media

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.

Journal Articles

An Evaluation method for plastic buckling of cantilever type pipes controlled by displacement loads, 1; Proposal of the estimation method and the criterion

Ando, Masanori; Tezuka, Taiji*; Nakamura, Toshio*; Okawa, Tomohiro*; Enuma, Yasuhiro*; Kawasaki, Nobuchika; Tsukimori, Kazuyuki

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 9 Pages, 2011/07

Journal Articles

An Evaluation method for plastic buckling of cantilever type pipes controlled by displacement loads, 2; Verification of proposal method by buckling test

Ando, Masanori; Tezuka, Taiji*; Nakamura, Toshio*; Okawa, Tomohiro*; Enuma, Yasuhiro*; Kawasaki, Nobuchika; Tsukimori, Kazuyuki

Proceedings of 2011 ASME Pressure Vessels and Piping Conference (PVP 2011) (CD-ROM), 8 Pages, 2011/07

Oral presentation

R&D MA separation processes for P&T system using ADS, 4; Novel soft-hard ligand for MA/Ln separation

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.

Oral presentation

R&D of MA separation processes for P&T system using ADS, 3; Counter-current continuous extraction tests of MA-Ln recovery process

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.

Oral presentation

R&D of MA separation processes for P&T system using ADS, 5; Examination of Novel Extractants for MA/Ln separation

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.

Oral presentation

Research and development of minor actinide separation process with novel extractants

Matsumura, Tatsuro; Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

R&D of MA separation processes for P&T system using ADS, 7; Examination of novel extractants for MA separation

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.

Oral presentation

R&D of MA separation processes for P&T system using ADS, 6; Development of MA recovery process with TDdDGA

Matsumura, Tatsuro; Suzuki, Hideya; Tsubata, Yasuhiro; Shibata, Mitsunobu; Kurosawa, Tatsuya; Kawasaki, Tomohiro; Sagawa, Hiroshi

no journal, , 

no abstracts in English

Oral presentation

R&D of MA separation processes for P&T system using ADS, 8; Examination of novel extractants for MA/RE separation

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.

Oral presentation

R&D of MA separation processes for P&T system using ADS, 9; Examination of novel extractants for MA/RE separation

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$$_{3}$$ 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).

Oral presentation

Current status of R&D on minor actinide separation process with CHON Extractants in JAEA

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.

Oral presentation

Current status of R&D on reprocessing and minor actinide separation process with CHON ligands in JAEA

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.

Oral presentation

Examination of novel extractants for MA separation

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.

Oral presentation

Solvent extraction process for reprocessing and minor actinides separation using CHON ligands

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.

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