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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

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

Optimization of disposal method and scenario to reduce high level waste volume and repository footprint for HTGR

Fukaya, Yuji; Goto, Minoru; Ohashi, Hirofumi; Nishihara, Tetsuo; Tsubata, Yasuhiro; Matsumura, Tatsuro

Annals of Nuclear Energy, 116, p.224 - 234, 2018/06

 Times Cited Count:1 Percentile:38.14(Nuclear Science & Technology)

Optimization of disposal method and scenario to reduce volume of High Level Waste (HLW) and the footprint in a geological repository for High Temperature Gas-cooled Reactor (HTGR) has been performed. It was found that HTGR has great advantages to reducing HLW volume and its footprint, which are high burn-up, high thermal efficiency and pin-in-block type fuel, compared with those of LWR and has potential to reduce those more in the previous study. In this study, the scenario is optimized, and the geological repository layout is designed with the horizontal emplacement based on the KBS-3H concept instead of the vertical emplacement based on KBS-3V concept employed in the previous study. As a result, for direct disposal, the repository footprint can be reduced by 20 % by employing the horizontal without change of the scenario. By extending 40 years for cooling time before disposal, the footprint can be reduced by 50 %. For disposal with reprocessing, the number of canister generation can be reduced by 20 % by extending cooling time of 1.5 years between the discharge and reprocessing. The footprint per electricity generation can be reduced by 80 % by extending 40 years before disposal. Moreover, by employing four-group partitioning technology without transmutation, the footprint can be reduced by 90 % with cooling time of 150 years.

Journal Articles

Separation of Ru(III), Rh(III) and Pd(II) from nitric acid solutions using ion-exchange resins bearing carboxylic betaine

Suzuki, Tomoya; Morita, Keisuke; Sasaki, Yuji; Matsumura, Tatsuro

Separation Science and Technology, 51(17), p.2815 - 2822, 2016/09

 Percentile:100(Chemistry, Multidisciplinary)

To understand the adsorption properties of styrene-divinylbenzene copolymer functionalized with ${it N,N,N}$-trimethylglycine, AMP03, the adsorption behaviors for platinoid ions (Ru(III), Rh(III), and Pd(II)) were examined. Furthermore, we performed adsorption experiments using sample solutions with adding triethylamine, thiourea, and ${it N,N,N}$-trimethylglycine. Based on the adsorption data obtained in this study, we performed chromatographic experiments. The results indicated that all platinoid ions in the feed solution completely adsorbed on AMP03, and almost 80% of the adsorbed platinoid ions were recovered. These results show that AMP03 has the potential to recover Ru(III), Rh(III), and Pd(II) from high-level liquid waste.

JAEA Reports

Status and future plan of research and development on partitioning and transmutation technology for long-lived nuclides in JAERI

Oigawa, Hiroyuki; Nishihara, Kenji; Minato, Kazuo; Kimura, Takaumi; Arai, Yasuo; Morita, Yasuji; Nakayama, Shinichi; Katakura, Junichi

JAERI-Review 2005-043, 193 Pages, 2005/09

JAERI-Review-2005-043.pdf:16.13MB

JAERI has been conducting research and development on partitioning and transmutation (P&T) technology for long-lived nuclides to develop the double-strata fuel cycle concept, in accordance with the Atomic Energy Commission's "Research and Development of Technologies for Partitioning and Transmutation of Long-lived Nuclides - Status and Evaluation Report" issued in 2000. The double-strata fuel cycle concept consists of four major processes: partitioning, fuel fabrication, transmutation, and fuel processing. The five-year achievement and future perspectives for the technology on these processes are presented in this report. It also provides an analytical study on impacts of introducing P&T technology on waste management, and on deployment of P&T for the future nuclear energy system.

Journal Articles

Development of ARTIST process, extraction and separation of actinides and fission products by TODGA

Sasaki, Yuji; Sugo, Yumi; Suzuki, Hideya*; Kimura, Takaumi

Proceedings of International Conference ATALANTE 2004 Advances for Future Nuclear Fuel Cycles (CD-ROM), 4 Pages, 2004/06

no abstracts in English

Journal Articles

R&D on nuclear transmutation, A; Partitioning of high-level radioactive waste

Morita, Yasuji

Genshikaku Kenkyu, 47(6), p.21 - 30, 2003/06

This paper describes the present state and future prospect of research and development on the separation of long-lived radionuclides from high-level waste (partitioning), which is indispensable for the transmutation of those nuclides. The main items described are composition of high-level waste, selection of elements to be separated, the purpose of partitioining, and development of partitioning process in JAERI.

Journal Articles

A Process of spent nuclear fuel treatment with the interim storage of TRU by use of amidic extractants

Tachimori, Shoichi; Suzuki, Shinichi; Sasaki, Yuji

Nippon Genshiryoku Gakkai-Shi, 43(12), p.1235 - 1241, 2001/12

 Times Cited Count:25 Percentile:12.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Radioactive wastes generated from JAERI partitioning-transmutation cycle system

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 6 Pages, 2001/09

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as $$^{14}$$C and $$^{59}$$Ni and spallation products of Pb-Bi coolants such as $$^{210}$$Po (10$$^{18}$$ Bq/yr) are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste.

Journal Articles

Radioactive wastes generated from JAERI partitioning-transmutation cycle system

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 6 Pages, 2001/00

no abstracts in English

Journal Articles

Radioactive wastes generated from double-strata nuclear fuel cycle for partitioning and transmutation

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

KURRI-KR-57, p.55 - 62, 2000/11

no abstracts in English

Journal Articles

Development of novel extractants for actinide separation

Tachimori, Shoichi

Nippon Genshiryoku Gakkai-Shi, 42(11), p.1124 - 1129, 2000/11

 Times Cited Count:1 Percentile:19.43(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Proceedings of the 4th NUCEF Seminar; 18 Feb. 2000, JAERI Tokai, Japan

4th NUCEF Seminar Working Group

JAERI-Conf 2000-012, 52 Pages, 2000/07

JAERI-Conf-2000-012.pdf:5.47MB

no abstracts in English

JAEA Reports

Cold and semi-hot tests of 4-group partitioning process at NUCEF

Morita, Yasuji; Yamaguchi, Isoo; Fujiwara, Takeshi; Mizoguchi, Kenichi*; Kubota, Masumitsu*

JAERI-Research 2000-024, 55 Pages, 2000/06

JAERI-Research-2000-024.pdf:2.24MB

no abstracts in English

Journal Articles

R&D on transmutation of long-lived nuclides

Mukaiyama, Takehiko

Mirai, (6), p.40 - 43, 1999/07

no abstracts in English

JAEA Reports

Development of partitioning process; Extraction behavior and third-phase formation of lanthanoid and iron with DIDPA

Watanabe, Masayuki; Morita, Yasuji; Kubota, Masumitsu

JAERI-Research 99-001, 18 Pages, 1999/01

JAERI-Research-99-001.pdf:0.78MB

no abstracts in English

Journal Articles

The First test of 4-group partitioning process with real high-level liquid waste

Morita, Yasuji; Yamaguchi, Isoo; ; *; Kubota, Masumitsu

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8 Pages, 1999/00

no abstracts in English

JAEA Reports

Development of partitioning method; Adsorption of cesium with mordenite in acidic media

L.Donnet*; Morita, Yasuji; Yamagishi, Isao; Kubota, Masumitsu

JAERI-Research 98-058, 63 Pages, 1998/10

JAERI-Research-98-058.pdf:2.19MB

no abstracts in English

JAEA Reports

Development of partitioning method; Confirmation of behavior of technetium in 4-group partitioning process by small scale experiment

Morita, Yasuji; Mizoguchi, Kenichi*; Yamaguchi, Isoo; ; Kubota, Masumitsu

JAERI-Research 98-046, 18 Pages, 1998/08

JAERI-Research-98-046.pdf:1.01MB

no abstracts in English

JAEA Reports

Proceedings of the 3rd NUCEF Seminar; 24 Feb. 1998, JAERI Tokai, Japan

JAERI-Conf 98-010, 47 Pages, 1998/06

JAERI-Conf-98-010.pdf:2.51MB

no abstracts in English

JAEA Reports

Development of partitioning method: Adsorption behaivor of Sr on titanic acid pelletized with binder

Mizoguchi, Kenichi*; Yamaguchi, Isoo; Morita, Yasuji; Yamagishi, Isao; ; Kubota, Masumitsu

JAERI-Research 98-026, 29 Pages, 1998/05

JAERI-Research-98-026.pdf:1.45MB

no abstracts in English

133 (Records 1-20 displayed on this page)