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Journal Articles

Current status and future plan of research and development on partitioning and transmutation based on double-strata concept in JAEA

Tsujimoto, Kazufumi; Sasa, Toshinobu; Maekawa, Fujio; Matsumura, Tatsuro; Hayashi, Hirokazu; Kurata, Masaki; Morita, Yasuji; Oigawa, Hiroyuki

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.657 - 663, 2015/09

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 of HLW is expected to be effective to mitigate the burden of the HLW disposal by reducing the radiological toxicity and heat generation. The Japan Atomic Energy Agency (JAEA) has been conducting the research and development on accelerator-driven subcritical system (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. This paper overviews the recent progress and future R&D plan of the study on the ADS and related fuel cycle technology in JAEA.

Journal Articles

Recent progress and future R&D plan of nitride fuel cycle technology for transmutation of minor actinides

Hayashi, Hirokazu; Nishi, Tsuyoshi; Takano, Masahide; Sato, Takumi; Shibata, Hiroki; Kurata, Masaki

NEA/NSC/R(2015)2 (Internet), p.360 - 367, 2015/06

Uranium-free nitride fuel was chosen as the first candidate for transmutation of long-lived minor actinides (MA) using accelerator-driven system (ADS) under the double strata fuel cycle concept by Japan Atomic Energy Agency (JAEA). The advantages of nitride fuel are good thermal properties and large mutual solubility among actinide elements. A pyrochemical process is proposed as the first candidate for the reprocessing of the spent nitride fuel, because this technique has some advantages over aqueous process, such as the resistance to radiation damage, which is an important issue for the fuels containing large amounts of highly radioactive MA. This paper overviews the recent progress and future R&D plan of the study on the nitride fuel cycle technology in JAEA.

Journal Articles

Nuclear energy and waste management; Pyroprocess for system symbiosis

Ogawa, Toru; Minato, Kazuo; Okamoto, Yoshihiro; Nishihara, Kenji

Journal of Nuclear Materials, 360(1), p.12 - 15, 2007/01

 Times Cited Count:13 Percentile:28.09(Materials Science, Multidisciplinary)

The actinide management has become a key issue in nuclear energy due to increasing proliferation concern and long-term environmental perception. The better way of waste management will be made by system symbiosis: a combination of light-water reactor and fast reactor and/or accelerator-driven transmutation system should be sought. The new recycling technology should be able to achieve good economy with smaller plants, which can process fuels from different types of reactors on a common technical basis. Pyroprocess with the use of molten salts is regarded as the strong candidate for such recycling technology. In JAEA, the first laboratory for the high temperature chemistry of transuranium elements, mainly Am and Cm, has been established. The fundamental data on the molten-salt chemistry of transuranium oxides and nitrides will be combined with the computer code for predicting the molten-salts electrolytic processes.

Journal Articles

Electrochemical behavior of actinides and actinide nitrides in LiCl-KCl eutectic melts

Shirai, Osamu*; Yamana, Hajimu*; Arai, Yasuo

Journal of Alloys and Compounds, 408-412, p.1267 - 1273, 2006/02

 Times Cited Count:33 Percentile:14.07(Chemistry, Physical)

no abstracts in English

JAEA Reports

Development of module for TRU high temperature chemistry (Joint research)

Minato, Kazuo; Akabori, Mitsuo; Tsuboi, Takashi; Kurobane, Shiro; Hayashi, Hirokazu; Takano, Masahide; Otobe, Haruyoshi; Misumi, Masahiro*; Sakamoto, Takuya*; Kato, Isao*; et al.

JAERI-Tech 2005-059, 61 Pages, 2005/09

JAERI-Tech-2005-059.pdf:20.67MB

An experimental facility called the Module for TRU High Temperature Chemistry (TRU-HITEC) was installed in the Back-end Cycle Key Elements Research Facility (BECKY) of the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) for the basic studies of the behavior of the transuranium elements (TRU) in pyrochemical reprocessing and oxide fuels. TRU-HITEC consists of three alpha/gamma cells shielded by steel and polyethylene and a glove box shielded by leaded acrylic resin, where experimental apparatuses have been equipped and a high purity argon gas atmosphere is maintained. In the facility 10 g of $$^{241}$$Am as well as the other TRU of Np, Pu and Cm can be handled. This report summarizes the outline, structure, performance and interior apparatuses of the facility, and is the result of the joint research between the Japan Atomic Energy Research Institute and three electric power companies of Tokyo Electric Power Co., Tohoku Electric Power Co. and the Japan Atomic Power Co.

Journal Articles

Local structure of molten CdCl$$_2$$ systems

Okamoto, Yoshihiro; Shiwaku, Hideaki; Yaita, Tsuyoshi; Suzuki, Shinichi; Minato, Kazuo; Tanida, Hajime*

Zeitschrift f$"u$r Naturforschung, A, 59a(11), p.819 - 824, 2004/11

The local structure of molten CdCl$$_2$$ and CdCl$$_2$$-KCl mixture was investigated by high-temperature XAFS technique. The nearest Cd-Cl distance decreases by melting. Similarly, the coordination number decreases from 6 to 4. It suggests that there is (CdCl$$_4$$)$$^{2-}$$ tetrahedral complex ion in the melt. It is concluded that the local structure is kept also in the mixture melt, since the same XAFS result as the pure melt was obtained.

JAEA Reports

Proceedings of the 3rd Workshop on Molten Salts Technology and Computer Simulation

Okamoto, Yoshihiro; Minato, Kazuo

JAERI-Conf 2004-008, 228 Pages, 2004/04

JAERI-Conf-2004-008.pdf:17.05MB

Applications of molten salts technology to separation and synthesis of materials have a potential to give us a civilized life, for example aluminium refinement. Recently, much attention is given to the pyrochemical reprocessing of spent nuclear fuels in the molten salt research field. On the other hand, computer simulation technique is expected to play an important role for supporting experimental works and predicting unknown physical properties in the molten salts application studies. Research group for Actinides Science, Department of Materials Science, Japan Atomic Energy Research Institute(JAERI), together with Reprocessing and Recycle Technology Division, Atomic Energy Society of Japan, organized the 3rd Workshop on Molten Salts Technology and Computer Simulation at Tokai Research Establishment, JAERI on December 16, 2003. Many molten salts researchers in Japan participated in the workshop and many useful presentations and discussions were performed.

Journal Articles

Recovery of alkali salt by supercritical fluid leaching method using carbon dioxide

Watanabe, Takeshi*; Tsushima, Satoru*; Yamamoto, Ichiro*; Tomioka, Osamu; Meguro, Yoshihiro; Nakashima, Mikio; Wada, Ryutaro*; Nagase, Yoshiyuki*; Fukuzato, Ryuichi*

Proceedings of 2nd International Symposium on Supercritical Fluid Technology for Energy and Environment Applications (Super Green 2003), p.363 - 366, 2004/00

Recovery of salts by supercritical fluid leaching (SFL) method using carbon dioxide was experimentally studied. It was confirmed that LiCl was recovered with a mixed fluid of carbon dioxide and methanol, and KCl and SrCl$$_2$$ were recovered with a mixed fluid of carbon dioxide, methanol and crown ether. The influence of crown ether for KCl and SrCl$$_2$$ extraction were found to increase in the order of 15-crown-5 (15C5) $$<$$ 18-crown-6 (18C6) $$<$$ dicychlohexyl-18-crown-6 (DC18C6). It is expected that other salts can be recovered selectively with a mixed fluid of carbon dioxide, methanol and suitable crown ether.

JAEA Reports

Proceedings of the 2nd Workshop on Molten Salts Technology and Computer Simulation

Okamoto, Yoshihiro; Minato, Kazuo

JAERI-Conf 2003-005, 186 Pages, 2003/06

JAERI-Conf-2003-005.pdf:10.42MB

Applications of molten salts technology to separation and synthesis of materials have been widely studied. Especially, much attention is given to the pyrochemical reprocessing of spent nuclear fuels. Computer simulation technique is expected to play an important role for supporting experimental works and predicting unknown physical properties in the molten salts application studies. Research group for Actinides Science, Department of Materials Science, Japan Atomic Energy Research Institute (JAERI), together with Reprocessing and Recycle Technology Division, Atomic Energy Society of Japan, organized the 2nd Workshop on Molten Salts Technology and Computer Simulation at Tokai Research Establishment, JAERI on December 3, 2002. Many molten salts researchers in Japan participated in the workshop and many useful presentations and discussions were performed.

Journal Articles

Pyrochemical reprocessing of nitride fuels

Shirai, Osamu*; Yamana, Hajimu*; Iwai, Takashi; Arai, Yasuo

Proceedings of Nuclear Fuel Cycle Technologies Closing the Fuel Cycle (CD-ROM), 7 Pages, 2003/00

no abstracts in English

Journal Articles

Present status and approach on advanced technologies of nuclear fuel, 3; Research and development of advanced recycle technology

Arie, Kazuo*; Abe, Tomoyuki*; Arai, Yasuo

Nippon Genshiryoku Gakkai-Shi, 44(8), p.593 - 599, 2002/08

no abstracts in English

Journal Articles

Nitride fuel

Arai, Yasuo

Nenryo Saikuru Gijutsu; 21-Seiki No Nenryo Saikuru No Kochiku Ni Mukete, p.119 - 126, 2002/05

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

Advanced recycle technology based on electrorefining of nitride fuel

Arai, Yasuo

Saishin Kaku Nenryo Kogaku; Kodoka No Genjo To Tembo, p.451 - 457, 2001/06

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, 2001/00

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 plutonium recovery process by molten salt electrorefining; Behavior of plutonium at liquid cadmium cathode

Iizuka, Masatoshi*; Inoue, Tadashi*; Iwai, Takashi; Shirai, Osamu; Arai, Yasuo

Denryoku Chuo Kenkyusho Hokoku (T99078), 24 Pages, 2000/06

no abstracts in English

Journal Articles

Pyrochemical reprocessing of nitride fuel

Arai, Yasuo; Ogawa, Toru

Kaku Nenryo, p.33_9 - 33_10, 2000/06

no abstracts in English

JAEA Reports

Development of system analysis code for pyrochemical process using molten salt electrorifining

Tozawa, Katsuhiro; ;

JNC-TN9400 2000-052, 110 Pages, 2000/04

JNC-TN9400-2000-052.pdf:4.39MB

This report describes accomplishment of development of a cathode processor calculation code to simulate the mass and heat transfer phenomena with the distillation process and development of an analytical model for cooling behavior of the pyrochemical process cell on personal computers. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. The cathode processor calculation code with distillation process was developed. A code validation calculation has been conducted on the basis of the benchmark problem for natural convection in a square cavity. Results by using the present code agreed well for the velocity-temperature fields, the maximum velocity and its location with the benchmark solution published in a paper. The functions have been added to advance the reality in simulation and to increase the efficiency in utilization. The test run has been conducted using the code with the above modification for an axisymmetric enclosed vessel simulating a cathode processor, and the capability of the distillation process simulation with the code has been confirmed. An analytical model for cooling behavior of the pyrochemical process cell was developed. The analytical model was selected by comparing benchmark analysis with detailed analysis on engineering workstation. Flow and temperature distributions were confirmed by the result of steady state analysis. In the result of transient cooling analysis, an initial transient peak of temperature occurred at balanced heat condition in the steady-state analysis. Final gas temperature distribution was dependent on gas circulation flow in transient condition. Then there were different final gas temperature distributions on the basis of the result of steady-state analysis. This phenomenon has a potential for it's own metastable condition. Therefore it was necessary to design gas cooling flow pattern without ...

JAEA Reports

ICONE-8 participation and investigation report of dry process in Argonne National Laboratory (ANL), USA

; Washiya, Tadahiro;

JNC-TN8420 2001-009, 48 Pages, 2000/04

JNC-TN8420-2001-009.pdf:0.58MB

ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...

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