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Journal Articles

Corrosion in nuclear fuel reprocessing plants; Corrosion in boiling nitric acid

Kato, Chiaki

Comprehensive Nuclear Materials, 2nd Edition, Vol.4, p.528 - 563, 2020/08

In spent fuel reprocessing plants, various nitric media are encountered throughout the PUREX process, used in the separation of fission products, uranium, and plutonium. The PUREX process is thus highly corrosive as it takes place at high temperatures under high concentrations of nitric acid solution containing oxidizing metal ions from spent fuel. In this review, the unique chemical properties of nitric acid are first described. Secondly, the process of oxidizing power generation in boiling nitric acid under heat transfer is described using the redox potential and a thermodynamic model of boiling nitric acid. Finally, the corrosion behavior and corrosion acceleration mechanism specific to the reprocessing environments are described from the perspective of solution chemistry.

Journal Articles

A Novel microemulsion phase transition; Toward the elucidation of third-phase formation in spent nuclear fuel reprocessing

Mu, J.*; Motokawa, Ryuhei; Akutsu, Kazuhiro*; Nishitsuji, Shotaro*; Masters, A. J.*

Journal of Physical Chemistry B, 122(4), p.1439 - 1452, 2018/02

 Times Cited Count:23 Percentile:73.37(Chemistry, Physical)

JAEA Reports

Handbook on Process and Chemistry of Nuclear Fuel Reprocessing, 3rd Edition

Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing

JAEA-Review 2015-002, 726 Pages, 2015/03

JAEA-Review-2015-002.pdf:43.63MB
JAEA-Review-2015-002(errata).pdf:0.21MB

The fundamental data on spent nuclear fuel reprocessing and related chemistry was collected and summarized as a new edition of "Handbook on Process and Chemistry of Nuclear Fuel Reprocessing". The purpose of this handbook is contribution to development of the fuel reprocessing and fuel cycle technology for uranium fuel and mixed oxide fuel utilization. Contents in this book was discussed and reviewed by specialists of science and technology on fuel reprocessing in Japan.

Journal Articles

Technetium separation for future reprocessing

Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu; Morita, Yasuji

Journal of Nuclear and Radiochemical Sciences, 6(3), p.271 - 274, 2005/12

Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO$$_{2}$$ fuel with burn-up of 44 GWd/t. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be almost quantitatively extracted from a dissolver solution and that Tc can also be almost quantitatively recovered by scrubbing. Further, it was clearly presented from the calculation results of ESSCAR that the extraction mechanism of Tc is dominated by the synergistic effect of Zr and U.

Journal Articles

Reprocessing technologies of the High Temperature Gas-cooled Reactor (HTGR) fuel

Sumita, Junya; Ueta, Shohei; Kunitomi, Kazuhiko; Yoshimuta, Shigeharu*; Sawa, Kazuhiro

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.546 - 554, 2003/12

A High Temperature Gas-Cooled Reactor (HTGR) is particularly attractive due to capability of producing high temperature helium gas and its inherent safety characteristic. Research and development of high temperature gas turbine plant and high temperature heat utilizing technology are now undergoing. The High Temperature Engineering Test Reactor (HTTR) is a research facility constructed by the Japan Atomic Energy Research Institute. This paper describes reprocessing technology of HTGR fuels. Coated fuel particles, consisted of a microsphere of low enriched UO$$_{2}$$ with TRISO particles, are used as the HTGR fuels. In order to reprocess HTGR fuels, a head-end process is needed and JAERI had confirmed jet-grind method as basic technologies of the head-end process. Since Purex method can be used after the head-end process, a reprocessing system for the HTGR fuels could be established. Also the preliminary study on the methodology for disposing graphite blocks in a HTGR was carried out, and its evaluation results were briefly presented.

Journal Articles

Research committee on Ruthenium and Technetium Chemistry in PUREX System, Organized by the Atomic Energy Society of Japan

Matsumoto, Shiro*; Uchiyama, Gunzo; Ozawa, Masaki*; Kobayashi, Y.*; Shirato, K.*

Radiochemistry, 45(3), p.219 - 224, 2003/05

no abstracts in English

Journal Articles

Extraction behavior of TRU elements in the nuclear fuel reprocessing

Hotoku, Shinobu; Asakura, Toshihide; Mineo, Hideaki; Uchiyama, Gunzo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.313 - 316, 2002/11

no abstracts in English

Journal Articles

Long-lived nuclide separation for advancing back-end fuel cycle process

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Iizuka, Masaru*; Fujisaki, Susumu; Isogai, Hikaru; Ito, Yoshinori*; Sato, Makoto; Hosoya, Noriaki

Journal of Nuclear Science and Technology, 39(Suppl.3), p.925 - 928, 2002/11

no abstracts in English

Journal Articles

Development of an advanced reprocessing process of spent nuclear fuel

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.483 - 488, 2002/00

no abstracts in English

JAEA Reports

Handbook on process and chemistry of nuclear fuel reprocessing

Department of Fuel Cycle Safety Research

JAERI-Review 2001-038, 600 Pages, 2001/12

JAERI-Review-2001-038.pdf:19.64MB

no abstracts in English

Journal Articles

Advanced technologies for long-lived nuclides separation in reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 8 Pages, 2001/09

no abstracts in English

Journal Articles

Solvent extraction behaviors of minor nuclides in nuclear fuel reprocessing process

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Mineo, Hideaki; Kamei, Kazushige; Watanabe, Makio; Fujine, Sachio

Journal of Radioanalytical and Nuclear Chemistry, 246(3), p.683 - 688, 2000/12

 Times Cited Count:10 Percentile:59.01(Chemistry, Analytical)

no abstracts in English

Journal Articles

PARC process for an advanced PUREX process

Uchiyama, Gunzo; Mineo, Hideaki; Hotoku, Shinobu; Asakura, Toshihide; Kamei, Kazushige; Watanabe, Makio; Nakano, Yuji*; Kimura, Shigeru; Fujine, Sachio

Progress in Nuclear Energy, 37(1-4), p.151 - 156, 2000/12

 Times Cited Count:7 Percentile:48.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study of safety aspects for pyrochemical reprocessing systems

;

JNC TN9400 2000-051, 237 Pages, 2000/04

JNC-TN9400-2000-051.pdf:8.14MB

In this study, we have proposed the concept of safety systems (solutions of safety problems) in pyrochemical reprocessing systems (lt consists of pyrochemical reprocessing methods and the injection casting process for the metal fuel fabrication, or vibro-packing process for the oxide fuel fabrication.) which has different concept from the existing PUREX reprocessing method and pellet fuel fabrication process. And we performed its safety evaluations. FoIlowing the present Japanese safety regulations for reprocessing facilities, we pointed out functions, design requirements and equipments relating to its safety systems and picked up subjects. For the survey of safety evaluations, we first selected anticipated events and accident events, and second by evaluated 6the correspondence of the limitation of the public exposure to the accidents above, by using two parameters, the safety design parameter (the filter performance to confine radioactive matelials) and the leak inventory of radioactivities, and last by picked up its problems. ln addition to the above evaluations we performed basic criticality analyses for its systems to utilize these results for the design and evaluation of the criticality safety management system. Thus this study specified the concept of safety systems for pyrochemical reprocessing processes and then issues in order to establish safety design policies (matters which must consider for the safety design) and guides and to advance more definite safety design.

JAEA Reports

Study on the nuclide behavior in nuclear fuel recycling system

Fujii, Toshiyuki*; *

JNC TJ9400 2000-003, 36 Pages, 2000/02

JNC-TJ9400-2000-003.pdf:1.36MB

For establishing a recycling system based on low-decontamination, the distribution behaviors of radionuclides in the process are essential information for the design of the system. Molybdenum and palladium are less radioactive fission products, but attention should be paid to them because they are likely to extremely affect the performance of the recycled fuels. In this context, in this study, the extraction behaviors of molybdenum and palladium under conditions of PUREX and TRUEX extraction process were experimentally studied, and their chemical mechanisms were discussed. In cojunction with the extraction experiments, absorption spectrometry was applied to identify the related species and the extraction mechanism. As a result, knowledge for the distribution characteristics of molybdenum and palladium in PUREX and TRUEX process was reinforced.

JAEA Reports

Study of assessing aqueous reprocessing process for the pipeless reprocessing plant

*; *; Fumoto, Hiromichi*; *; *

JNC TJ9400 2000-001, 112 Pages, 2000/02

JNC-TJ9400-2000-001.pdf:6.67MB

The purpose of this study is to investigate the possibility of new reprocessing process for the purpose of introducing pipeless plant concept, where aqueous separation methods other than solvent extraction method are adopted in order to develop more economical FBR fuel (MOX fuel) reprocessing process. At it's first stage, literature survey on precipitation method, crystallization method and ion-exchange method was performed. Based on the results, following processes were candidated for pipeless reprocessing plant. (1)The process adopting crystallization method and peroxide precipitation method (2)The process adopting oxalate precipitation method (3)The process under mild aqueous conditions (crystallization method and precipitation method) (4)The process adopting crystallization method and ion-exchange method (5)The process adopting crystallization method and solvent extraction method The processes (1)$$sim$$(5) were compared with each others in terms of competitiveness to the conventional reference process, and merits and demerits were evaluated from the viewpoint of applicability to pipeless reprocessing plant, safety, economy, Efficiencies in consumption of Resources, non-proliferation, and, Operation and Maintenance. As a result, (1)The process adopting crystallization method and peroxide precipitation method was selected as the most reasonable process to pipeless plant. Preliminary criticality safety analyses, main process chemical flowsheet, main equipment list and layout of mobile vessels and stations were reported for the (1) process.

JAEA Reports

The Research on the behavior of the minor products in the PUREX Process

Koga, Jiro*; Shinzato, Takushi*

JNC TJ8400 2000-054, 48 Pages, 2000/02

JNC-TJ8400-2000-054.pdf:1.23MB

The "STELLA" which is a tool for simulation of dynamical systems applied to the numerical simulation of the behavior of minor constituent, such as hydrazoic acid, forming and extinguishing on the operation of reprocessing process. The concentration of hydrazoic acid forming by the reaction of nitrite and hydrazine were determined by use of STELLA after the determination of concentration of main constituents by MIXSET-X. The results from simulation is shown that the STELLA is applicable to the numerical simulation of the behavior of minor constituent.

Journal Articles

Management of minor long-lived nuclides in nuclear fuel reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Kamei, Kazushige; Watanabe, Makio; Fujine, Sachio

Proceedings of 12th Pacific Basin Nuclear Conference (PBNC 2000), Vol.1, p.531 - 538, 2000/00

no abstracts in English

Journal Articles

Reduction of minor nuclides in nuclear fuel reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Kamei, Kazushige; Watanabe, Makio; Fujine, Sachio

Proceedings of 2nd International Conference on Safewaste 2000, Vol.2, p.689 - 700, 2000/00

no abstracts in English

Journal Articles

Development of treatment technology for carbon-14 in dissolver off-gas of spent fuel

Mineo, Hideaki; ; *; Uchiyama, Gunzo; Fujine, Sachio

Proc. of 7th Int. Conf. on Radioactive Waste Mamagement and Environmental Remediation (ICEM '99)(CD-ROM), 3 Pages, 1999/00

no abstracts in English

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