Effects of diluents on the separation of minor actinides from lanthanides with tetradodecyl-1,10-phenanthroline-2,9-diamide from nitric acid medium

Tsutsui, Nao; Ban, Yasutoshi; Suzuki, Hideya*; Nakase, Masahiko*; Ito, Sayumi*; Inaba, Yusuke*; Matsumura, Tatsuro; Takeshita, Kenji*

Analytical Sciences, 36(2), p.241 - 246, 2020/02

https://doi.org/10.2116/analsci.19P275

To investigate the effective separation of actinides (Ans) from lanthanides (Lns), single-stage batch extraction experiments were performed with a novel extractant, tetradodecyl-1,10-phenanthroline-2,9-diamide (TDdPTDA) with various diluents such as 3-nitrobenzotrifluoride (F-3), nitrobenzene, and -dodecane for Am, Cm, and Lns. The extraction kinetics with TDdPTDA was rapid enough to perform the actual extraction flow sheet. The slopes of the distribution ratio versus TDdPTDA concentration and the distribution ratio versus nitric acid concentration were similar for F-3 and nitrobenzene systems but different from -dodecane system. These differences were attributed to the characteristics of the diluents. This study reveals high distribution ratios of Am ( ) and Cm ( ) for TDdPTDA, with the high separation factors (s) of Am from Lns enough for their separation.

Research for spectroscopy of fuel debris using superconducting phase transition edge sensor microcalorimeter; Measurement experiment and simulated calculation (Joint research)

Takasaki, Koji; Yasumune, Takashi; Onishi, Takashi; Nakamura, Keisuke; Ishimi, Akihiro; Ito, Chikara; Osaka, Masahiko; Ono, Masashi*; Hatakeyama, Shuichi*; Takahashi, Hiroyuki*; et al.

JAEA-Research 2013-043, 33 Pages, 2014/01

JAEA-Research-2013-043.pdf:13.81MB

In the Fukushima Daiichi Nuclear Power Plant, it is assumed that the core fuels melted partially or wholly, and the normal technique of accounting for a fuel assembly is not applicable. Therefore, it is necessary to develop the transparent and rational technique of accounting in the process of collection and storage of fuel debris. In this research, an application of the superconducting phase Transition Edge Sensor microcalorimeter (TES microcalorimeter) is studied for the accounting of nuclear materials in the fuel debris. It is expected that the detailed information of nuclear materials and fission products in fuel debris is obtained by using a high-resolution characteristic of TES microcalorimeter. In this report, the principle of TES microcalorimeter, the measurement experiment using TES in JAEA, and the simulated calculation using the EGS5 code system are summarized.

Retention and release of tritium in BC irradiated as control rod of fast breeder reactor

Donomae, Takako; Ito, Masahiko*

Journal of Nuclear Science and Technology, 48(5), p.826 - 833, 2011/05

https://doi.org/10.3327/jnst.48.826

The release and retention of tritium generated in FBR control rods of BC irradiated to high fluence were investigated for temperatures up to 800C. The amounts of tritium retention were expressed as a function of fluence, and the results agreed approximately with the theoretically calculated values. In addition, the amounts of tritium could be approximately evaluated by simply measuring the radioactivity of Mn using germanium semiconductor detector, which is generated from Fe impurity in BC. The temperature at which the tritium begins to be released from BC was investigated by heating a specimen at a constant temperature increasing rate. It was found in this experiment that the tritium begins to be released from BC at 400C. From the results of this isochronal heating, diffusion coefficients of tritium in BC were derived.

Protected plutonium production by transmutation of minor actinides for peace and sustainable prosperity; Irradiation tests of Np and Np-U samples in experimental fast reactor JOYO (JAEA) and advanced thermal reactor ATR (INL)

Koyama, Shinichi; Osaka, Masahiko; Ito, Masahiko*; Sagara, Hiroshi*; Saito, Masaki*

Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.2356 - 2362, 2009/09

A project of Protected Plutonium Production was proposed by Tokyo-Tech as a part of non-proliferation research for Pu utilization to nuclear reactor. In order to validate this concept, two irradiation tests were performed. Experimental determination of Pu isotopes in Np samples irradiated in the experimental fast reactor JOYO was done to evaluate Pu production from Np under the fast neutron spectra. On the other hand, 2%, 5% and 10% Np containing U samples were also irradiated in Advanced Thermal Reactor of INL to evaluate the Pu production under thermal neutron region. The verified Np transmutation data can be used to design an Np-U mixed oxide fuel pellet for next phase Np-U fuel performance evaluations.

Aspects of Pu production in the experimental fast reactor JOYO

Osaka, Masahiko; Koyama, Shinichi; Tanaka, Kenya; Ito, Masahiko; Saito, Masaki*

Annals of Nuclear Energy, 32(10), p.1023 - 1031, 2005/07

https://doi.org/10.1016/j.anucene.2005.02.010

Experimental determination of Pu in Np samples irradiated in the experimental fast reactor JOYO was performed for the demonstration of Pu production in the fast reactor in the frame of protected plutonium production. Pu production in the sample was determined and was depended on the neutron spectrum in the range from typical fast reactor's one to nearly epi-thermal one. It is concluded that the fast reactor has high potential for the use of protected plutonium production, not also as the generator of the protected plutonium but also as the incinerator of excess Pu.

Current Status of PIE Activities in O-arai Engineering Center of JNC on FBR MOX Fuel

Koyama, Shinichi; Osaka, Masahiko; Namekawa, Takashi; Ito, Masahiko

Proceedings of 7th International Conference on Nuclear Criticality Safety (ICNC 2003), 0 Pages, 2003/10

Japan Nuclear Cycle Development Institute (JNC) is now totally promoting the development of commercialized fast reactors to realize stable supply of energy in future. One of the important items is to develop hign-performance fuel. For that purpose,it is e

Measurement of Burn-up in FBR MOX Fuel Irradiated up to High Burn-up

Koyama, Shinichi; Osaka, Masahiko; Sekine, Takashi; Morozumi, Katsufumi; Namekawa, Takushi;

Journal of Nuclear Science and Technology, 40(2), p.998 - 1013, 2003/02

https://doi.org/10.3327/jnst.40.998

None

Measurements of the depth profile of the refractive indices in oxide films on SiC by spectroscopic ellipsometry

Iida, Takeshi*; Tomioka, Yuichi*; Yoshimoto, Kimihiro*; Midorikawa, Masahiko*; Tsukada, Hiroyuki*; Orihara, Misao*; Hijikata, Yasuto*; Yaguchi, Hiroyuki*; Yoshikawa, Masahito; Ito, Hisayoshi; et al.

Japanese Journal of Applied Physics, Part 1, 41(2A), p.800 - 804, 2002/02

https://doi.org/10.1143/JJAP.41.800

no abstracts in English

The Fruits and Hope of The Experimental Fast Reactor "JOYO"

Miyakawa, Shunichi; Yanagisawa, Tsutomu; ; ; Mitsugi, Takeshi

P247, 247 Pages, 2002/00

None

Measurement of the Central Void Diameter in FBR MOX Fuel by the X-Ray Computer Tomography

Katsuyama, Kozo; Nagamine, Tsuyoshi; Matsumoto, Shinichiro;

Journal of Nuclear Science and Technology, 39(7), 804 Pages, 2001/00

https://doi.org/10.3327/jnst.39.804

None