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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

Study on gaseous effluent treatment for dissolution step of spent nuclear fuel reprocessing

Mineo, Hideaki; Iizuka, Masaru*; Fujisaki, Susumu; Hotoku, Shinobu; Asakura, Toshihide; Uchiyama, Gunzo

Proceeding of International Waste Management Symposium 2002 (WM '02) (CD-ROM), 9 Pages, 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

JAEA Reports

A Study on rare gas-oxygen reactions excited by low temperature plasma

Ogawa, Hiroaki; Kiuchi, Kiyoshi; Saburi, Tei; Fukaya, Kiyoshi

JAERI-Research 2001-023, 21 Pages, 2001/03

JAERI-Research-2001-023.pdf:1.98MB

no abstracts in English

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.

Journal Articles

Dissolution tests of spent fuel in the NUCEF cell including dissolver off-gas treatment

Mineo, Hideaki; Kihara, Takehiro; *; Kimura, Shigeru; *; ; Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; ; et al.

JAERI-Conf 99-004, p.498 - 507, 1999/03

https://jopss.jaea.go.jp/pdfdata/JAERI-Conf-99-004-Part1.pdf

no abstracts in English

Journal Articles

Study on gaseous effluent treatment during dissolusion tests of spent fuel

Mineo, Hideaki; Kihara, Takehiro; *; ; *; Kimura, Shigeru; Uchiyama, Gunzo; Hotoku, Shinobu; ; ; et al.

Proceedings of International Waste Management Symposium '99 (Waste Manegement '99) (CD-ROM), 6 Pages, 1999/03

no abstracts in English

JAEA Reports

Investigation of pyrometallurgical partitioning and extracting technology of irradiated fuel

Yumoto, Ryozo*; Yokochi, Yoji*; Koizumi, Masumichi*; Seki, Sadao*

PNC TJ9409 96-002, 93 Pages, 1996/03

PNC-TJ9409-96-002.pdf:2.64MB

The state of development of pyrometallurgical partitioning and extracting technology of irradiated fuel is investigated. Also in case of perfoming the test at O-arai engineering center, the contents of the test, equipments, structure and arragement of cells that equipments are installed, are studied. The purpose of the test is to confirm the realization of the process and behavior of FP and TRU elements, and off-gass that cannot be made dear by cold test. In this study it is assumed that 100g monju fuel (94,000MWd/t B.U, cooled for 550 days) per batch is treated. Four processes are picked up except for pin sectioning and powdering, as important subjects. They are as follows. (1)reduction of oxide fuel (2)electrorefining (3)cathode processing (4)extraction of TRU elements. And the outline of the test, blocked flow chart and the outline of equipment are clarified. And the outline of chart is drawn. Moreover, the specification of analitical equipments which are necessary to analyze the product is shown. From spent chloride, TRU and a part of FP elements are extracted and they are recycled for electrorefining and so on. The salt-waste including residual FP elements is kept in a receptacle after being absorbed into Zeorite and soldified. As the disposition of these tests, modified test cell in the existing FMF, modified concrete cell in AGF, new cell at B2F in the existing FMF and new cell at second auxiliary room in FMF extension are studied. As result of considering the disposition for equipment, the difficulty of reconstucting new cell including of equipments, method of mentenance, and equipments of ventilazion (Ar circumstance) including of management of off gas, and the plan of disposition, it is concluded that constructing iron cell into the second auxiliary room of FMF extension is best, because it is easy to construct safely, and the occurance of radioactive waste and the influence to other tests is little, and it is possible to examine more efficiently.