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Transmutation of long-lived radioactive nuclides including minor actinides (MA: Np, Am, Cm) is effective to reduce the burden of high level radioactive wastes and using repositories efficiently. Uranium-free nitride fuel has been chosen as the first candidate fuel for MA transmutation using accelerator-driven system (ADS) in Japan Atomic Energy Agency (JAEA) under the double strata fuel cycle concept. To improve the transmutation ratio of MA, reprocessing of spent MA fuel and reusing the recovered MA is necessary. Our target is to transmute 99% of MA arisen from commercial power reactor fuel cycle, with which the period until the radiotoxicity drops below that of natural uranium can be shorten from about 5000 years to about 300 years. Each reprocessing process is required to recover 99.9% of MA to meet the target. Typical composition of the solid solution type (MA,Pu,Zr)N fuel is considered as 30 wt.% of MA nitride, 20 wt.% of Pu nitride, and 50 wt.% of ZrN (dilution material to adjust the power density). Pyroprocessing has been proposed to adopt for reprocessing of the spent MA nitride fuel. This paper summarizes the status of our study on pyroprocessing of ZrN-based nitride fuels.

Oral presentation

Recent progress on development of pyroprocessing technology for minor actinide transmutation nitride fuels

Hayashi, Hirokazu; Sato, Takumi; Tateno, Haruka*; Akashi, Shin*; Shibata, Hiroki; Tsubata, Yasuhiro

no journal, ,

Japan Atomic Energy Agency (JAEA) has been developing the technology on transmutation of MA under the double strata fuel cycle concept. A combination of uranium-free Pu-MA-Zr nitride fuel and pyroprocessing has been chosen as the first candidate for MA transmutation fuel cycle using accelerator-driven system (ADS). This paper introduces the recent progress ondevelopment of pyroprocessing technology for MA transmutation nitride fuels. It contains a detailed design of the flowsheet on the electrorefining process of the spent fuels and the behavior of metal elements in renitridation process.

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Recovery of U by electrolysis of UN in LiCl-KCl eutectic melts

Preparation of UN microspheres by internal gelation process

Thermochemical modeling of actinide alloys related to advanced fuel cycles

Thermodynamic study of the dissolution of nitrogen in nitrogen-rich -U $_{2}$ N $_{3+x}$

Study on the formation of -U $_{2}$ N $_{3+x}$ using unstable ammonia; Reaction sequence and control of nitrogen activity

Anodic dissolution of uranium mononitride in lithium chloride-potassium chloride eutectic melt

Present status of TRU fuels behavior analysis and their data bases

Crystallographic study on the phase transition of -U $_{2}$ N $_{3}$

Lattice parameter of UN-PuN solid solution

Fabrication of uranium-plutonium mixed nitride fuel pins(89F-3A) for second irradiation test at JMTR

Non-stoichiometry in uranium sesquinitride

Formation of uranium nitride by the reaction of uranium hydride with nitrogen and ammonia

Porosity dependence of thermal conductivity of uranium mononitride

Equilibrium Nitrogen Pressures and Thermodynamic Properties of Uranium Sesquinitride

Magnetic and Electrical Properties of Uranium Carbonitride and Oxycarbide

Magnetic Susceptibility of Uranium Carbonitride

Porosity Dependence of Elastic Modulus of Uranium Nitride

Electrical properties of uranium carbonitride

Pyroprocessing of ZrN-based nitride fuels

Recent progress on development of pyroprocessing technology for minor actinide transmutation nitride fuels