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

Pyrochemical reprocessing of nitride fuel

Arai, Yasuo; Ogawa, Toru

Kaku Nenryo, p.33_9 - 33_10, 2000/06

no abstracts in English

Electrolysis of plutonium nitride in LiCl-KCl eutectic melts

Shirai, Osamu; Iwai, Takashi; Shiozawa, Kenichi; Suzuki, Yasufumi; Sakamura, Y.*; Inoue, Tadashi*

Journal of Nuclear Materials, 277(2-3), p.226 - 230, 2000/02

https://doi.org/10.1016/S0022-3115(99)00194-4

no abstracts in English

Research on nitride fuel and pyrochemical process for MA transmutation

Arai, Yasuo; Ogawa, Toru

Proceedings of 6th OECD/NEA International Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, p.445 - 457, 2000/00

no abstracts in English

Designstudy on advanced nuclear fuel recycle system; Conceptual design study of recycle system using molten salt

; Kakehi, Isao; Moro, Satoshi; ; ; ;

JNC TN9400 98-003, 422 Pages, 1998/10

JNC-TN9400-98-003.pdf:21.36MB

Advanced recycle system engineering group of OEC has being carried out a design study of the advanced nuclear fuel recycle system using molten salt (electro-metallurgical process). This system is aiming for improvements of fuel cycle economy and reduction of environmental burden (MA recycles, Mimmum of radioactive waste disposal), and also improvement of safety and nuclear non-proliferation. This report describes results of the design study that has been continued since December 1996. (1)A design concept of the advanced nuclear fuel recycle system, that is a module type recycle system of pyrochemical reprocessing and fuel re-fabrication was studied. The module system has advantage in balance of Pu recycle where modules are constructed in coincidence with the construction plan of nuclear power plants, and also has flexibility for technology progress. A demonstration system, minimum size of the above module, was studied. This system has capacity of 10 tHM/y and is able to demonstrate recycle technology of MOX fuel, metal fuel and nitride fuel. (2)Each process of the system, which are pyrochemical electrorefining system, cathode processor, de-cladding system, waste disposal system, etc., were studied. In this study, capacity of an electrorefiner was discussed, and vitrification experiment of molten salt using lead-boric acid glass was conducted. (3)A hot cell system and material handling system of the demonstration system was studied. A robot driven by linear motor was studied for the handling system, and an arrangement plan of the cell system was made. Criticality analysis in the cell system and investigation of material accountancy system of the recycle plant were also made. This design study will be continued in coincidence with design study of reactor and fuel, aiming to establish the concept of FBR recycle system.

Electrochemical behavior of actinide ions in LiCl-KCl eutectic melts

Shirai, Osamu; Iwai, Takashi; Suzuki, Yasufumi; Sakamura, Y.*; *

Journal of Alloys and Compounds, 271-273, p.685 - 688, 1998/00

https://doi.org/10.1016/S0925-8388(98)00187-X

no abstracts in English

Research and development of nitride fuel cycle for TRU burning

; Ogawa, Toru; Osugi, Toshitaka; Arai, Yasuo; Mukaiyama, Takehiko

Proc. of 4th Int. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transm, 0, p.178 - 188, 1997/00

no abstracts in English

Research on actinide mononitride fuel

Arai, Yasuo; ; Handa, Nuneo

Global 1995, Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems,Vol. 1, 0, p.538 - 545, 1995/00

no abstracts in English