JAEA    Nucl. Sci. and Eng. Center    Research Group for MA Transmutation Fuel Cycle

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[Research Activities]

    Partitioning and Transmutation (P&T) technology is to separate elements in high level radioactive waste discharged from the reprocessing plant depending on intended use to transmute long-lived nuclides to short-lived or stable ones. This technology aims at reducing the burden of high-level waste and to use the repository efficiently.

    In the Sector of Nuclear Science Research, JAEA, research and development of the technology for the transmutation of highly radioactive long-lived nuclides including minor actinides (MA: neptunium (Np), americium (Am), and curium (Cm)), using a dedicated Accelerator-Driven System (ADS) have been carried out.

    To transmute MA using ADS, neutrons produced by spallation of accelerated proton beam to metal target will be supplied successively to subcritical core to keep fission chain reactions of MA and other elements in the core.

    The core has fuel assemblies consists of bunches of fuel pins which have fuel pellets in the claddings like the fuels of other types of nuclear reactors. The composition and the chemical form of the fuel pellets containing MA elements should be appropriate for MA transmutation. Uranium-free MA nitride has been selected as the first candidate for the MA transmutation fuel.

    Previous feasibility study on transmutation system shows that only 20 % of MA in the fuel can be transmuted in one burning cycle of about 2 years. To increase the transmutation ratio, reprocessing of spent MA transmutation fuels and reuse of MA elements existing in the spent MA transmutation fuels are necessary. Therefore, fuel fabrication, transmutation, and reprocessing should be repeated in the MA transmutation fuel cycle as shown in Figure 1.

    “Research Group for MA Transmutation Fuel Cycle” has been carrying out research and development for the technology on reprocessing of spent MA transmutation fuel shown in Figure 2 to recover and reuse the MA in the spent fuels. One of our concerns is on pyrochemical treatment technology, in which molten salts and liquid metals are used as solvents; this technique is suitable for treatment of MA transmutation nitride fuels.


Research and Development to Reduce Radioactive Waste by Accelerator
- Current Status and Prospects for Partitioning and Transmutation Technology -

Atomic Energy Society of Japan,
Reprocessing and Recycle Technology Division
Text "Nuclear Fuel Cycle"
8-3 ADS Fuel Cycle (in Japanese)

The
  Figure 1. Schematic Diagram of the MA Transmutation Fuel Cycle Using ADS

The
  Figure 2. Schematic Diagram of the Pyrochemical Reprocessing Process of the Spent MA Nitride Fuel for ADS

[Recent Topics]

• Technological Development of Renitridation of Plutonium Recovered in Liquid Cadmium

• Preparation of Minor Actinide Chlorides without the Use of Corrosive Gases

• Evaluating Thermodynamic Data on Intermetallic Compounds with Electrochemical Techniques

• Preparation of a High-purity Curium Sample at the Milligram Scale

• Development of the Technology for Pyrochemical Treatment of MA Nitride Fuel

• Development of a Chlorination Method for Slightly Soluble Components

Publication

Journals, Proceedings, Technical Reports


-2020-

H. Tateno, T. Sato, Y. Tsubata, H. Hayashi
Material Balance Evaluation of Pyroprocessing for MA Transmutation Nitride Fuel
J. Nucl. Sci. Technol., 57, 224-235 (2020).

-2019-

H. Hayashi, T. Sato, H. Tateno, S. Akashi, H. Shibata, Y. Tsubata
Recent Progress on Development of Pyroprocessing Technology for Minor Actinide Transmutation Nitride Fuels
Proc. Global2019, pp. 654-658.

-2018-

H. Hayashi, R. Chiba
Dissolution and Chemical Analysis of Zr-based Lanthanide Nitrides
Progress in Nuclear Science and Technology, 5, 196-199 (2018).

-2017-

T. Nishi, H. Hayashi, T. Sato, M. Takano
Self-irradiation Effect on Thermal Conductivity of Zr0.70Pu0.25Cm0.05N Solid Solution
J. Nucl. Mater. 486, 167-171 (2017).
H. Hayashi, T. Sato, H. Shibata, Y. Tsubata
Research and Development on Pyrochemical Treatment of Spent Nitride Fuels for MA Transmutation in JAEA
Fourteenth International Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (14IEMPT)
NEA/NSC/R(2017)3 (Internet), 427-432 (2017).
T. Suzuki, M. Takeuchi, S. Watanabe, T. Matsumura, M. Iizuka, T. Sato
Present State of Partitioning and Transmutation of Long-lived Nuclides (2); Partitioning Methods of Minor Actinides from Spent Nuclear Fuel
Journal of the Atomic Energy Society of Japan, 59(9), 26-30 (2017).
H. Hayashi, T. Sato, Y. Tsubata
Development of the Technology for Pyroprocessing of Minor Actinide Nitride Fuel
Proc. GLOBAL2017 (2017).
K. Tsujimoto, H. Hayashi, T. Matsumura, M. Takano
Current Status and Future Plan of Research and Development on Partitioning and Transmutation Based on Double-strata Concept in JAEA
Proc. GLOBAL2017 (2017).

-2015-

H. Hayashi, M. Akabori, K. Minato
Electrochemical Behavior of Americium in NaCl - 2 CsCl Melt
5th Asia-Pacific Symposium on Radiochemistry (APSORC '13)
Journal of Radioanalytical and Nuclear Chemistry, 303 (2015) 1331-1334.
T. Sato, H. Shibata, H. Hayashi, M. Takano, M. Kurata
Chlorination of UO2 and (U, Zr)O2 Solid Solution Using MoCl5
J. Nucl. Sci. Technol., 52 (10), 1253-1258 (2015).
H. Shibata, H. Hayashi, T. Koyama
Evaluation of Apparent Standard Potentials of Curium in LiCl-KCl Eutectic Melt
Electrochemistry, 83(7), 532 - 536 (2015)
K. Tsujimoto, T. Sasa, F. Maekawa, T. Matsumura, H. Hayashi, M. Kurata, Y. Morita, H. Oigawa
Current Status and Future Plan of Research and Development on Partitioning and Transmutation based on Double-Strata Concept in JAEA
GLOBAL 2015 - 21st International Conference on Nuclear Fuel Cycle for a Low-carbon Future
Proceedings of Global 2015, 657 -663 (2015)
T. Sato, H. Hayashi, T. Nishi, M. Kurata
An Innovative Anode Concept for Improving Anodic Dissolution Rate of Nitride Fuel in Electrorefining Process
GLOBAL 2015 - 21st International Conference on Nuclear Fuel Cycle for a Low-carbon Future
Proceedings of Global 2015, 1234 -1239 (2015).
H. Hayashi, T. Nishi, M. Takano, T. Sato, H. Shibata, M. Kurata
Development of Nitride Fuel Cycle Technology for Transmutation of Minor Actinides
GLOBAL 2015 - 21st International Conference on Nuclear Fuel Cycle for a Low-carbon Future
Proceedings of Global 2015, 1811 - 1817 (2015).
H. Hayashi, T. Nishi, M. Takano, T. Sato, H. Shibata, M. Kurata
Recent progress and future R&D plan of nitride fuel cycle technology for transmutation of minor actinides
13th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
Proceedings of 13th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation, 370-377 (2015).

-Before 2014-

Please see below.

• Publication of Research Group for High Temperature Science on Fuel Materials

• Publication of Research Group for Partitioning

Cooperation

Joint Research

2019 - 2021
Ibaraki University
Fundamental Study on Physical Property Measurements of High Temperature Melts
2018 -
Tokyo Institute of Technology
Fundamental Study on Aqueous Reprocessing of Nitride Fuel

Competitive Research Funding

2016 - 2019
Ministry of Education, Culture, Sports, Science and Technology (MEXT), Japan
R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

Members


Group Leader

HAYASHI Hirokazu

Members

TSUBATA Yasuhiro

NAKAMURA Satoshi

MISHIMA Ria

Collaborators

OTOBE Haruyoshi

SHIBATA Hiroki

SATO Takumi

Contact Information

Japan Atomic Energy Agency
Sector of Nuclear Science Research
Nuclear Science Research Institute
Nuclear Science and Engineering Center
Partitioning and Transmutation Technology Division
Research Group for MA Transmutation Fuel Cycle
2-4 Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan

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