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Journal Articles

Development of U and Pu co-processing process; Demonstration of U, Pu and Np Co-recovery with centrifugal contactors

Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sasaki, Shunichi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04

The Co-processing process is the extraction process to recover Pu/U mixed product solution with given Pu/U ratio for improving of nuclear proliferation resistance. In addition, Np is also recovered with U and Pu because Np is one of minor actinides and a long-lived radionuclide and Np has the extractability into TBP solvent. Development of its flowsheet achieves to decrease environmental effect of waste materials. The orientation of development about Co-processing process is to demonstrate of reprocessing the future spent fuels from a LWR, a LWR-MOX hybrid, and a FR-MOX with one cycle. We demonstrated by use of miniature reflux-type centrifugal contactors at the partitioning unit. The test conditions of the Pu/U ratio in the loaded solvents were 1%, 3%, and 5% considering the composition of spent fuels. We used the HAN as the reductant of Np (VI) for back extraction. The results of these tests were very good. We got the prospect of U, Pu, and Np Co-processing flowsheet.

Oral presentation

MOX reprocessing at TRP, 5; Evaluation for temperature of plutonium product in storage

Kurabayashi, Kazuaki; Kawaguchi, Yoshihito; Takaya, Akikazu; Morimoto, Kazuyuki; Kanamori, Sadamu; Omori, Eiichi

no journal, , 

Plutonium product recovered from Fugen MOX type B spent fuel is measured temperature at Tokai Reprocessing Plant. And we studied difference between estimated by ORIGEN and analytical value of relative promotion on Pu, moreover, we studied calculation model because of the difference between initial evaluation and temperature of Pu product.

Oral presentation

Reinforcement of safety measures for the earthquake disaster of the Tokai Reprocessing Plant

Kuroda, Yasuji; Kurabayashi, Kazuaki; Otani, Takehisa; Tomiyama, Masahiro; Miura, Takatomo; Namatame, Toshihiro

no journal, , 

It was based on teachings of the Fukushima Daiichi Nuclear Power Plant accident, and the view and concrete measure against security were arranged supposing major accidents, such as all the power supply loss by the earthquake and tsunami, about decay heat removal, such as highly radioactivity waste fluid in the Tokai reprocessing facility, and plutonium solution, and the measure against hydrogen exhaust gas. Moreover, while verifying the validity of safety measures, an example of verification of the data used for safety evaluation was shown.

Oral presentation

Emergency safety measures at the Tokai Reprocessing, 2

Ouchi, Masayuki; Hoshi, Takahiro; Sasaki, Shunichi; Isobe, Hiroyasu; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Obu, Tomoyuki

no journal, , 

Plutonium nitrate solution is stored in tanks that have cooling system to prevent boiling accident by decay heat and scavenging system to prevent explosion of hydrogen generated by radiolysis. These systems are designed to be provided power from emergency power generators at the Tokai Reprocessing Plant (TRP) when commercial power is lost. In addition, some apparatus (mobile power generators and nitrogen gas cylinder to scavenge hydrogen, etc.) are recently deployed at TRP on the basis of power loss in Fukushima Daiichi nuclear accident. In this report, these safety measures for emergency are shown.

Oral presentation

Measurement of the hydrogen concentration in the vessel off-gas generated radiolytically from Pu storage tanks

Hoshi, Takahiro; Nagaoka, Shinichi; Kudo, Atsunari; Ouchi, Masayuki; Isobe, Hiroyasu; Obu, Tomoyuki; Kurabayashi, Kazuaki

no journal, , 

no abstracts in English

Oral presentation

Development of U and Pu co-processing process; Studies of U, Pu and Np co-recovery flow sheets with centrifugal contactors

Kurabayashi, Kazuaki; Kudo, Atsunari; Sato, Takehiko; Tada, Kazuhito*; Obu, Tomoyuki

no journal, , 

We are developing Np recovery with U and Pu in co-processing process (U and Pu co-recovery) because Np is one of minor actinides and a long-lived radionuclide. It is reported the flow sheet of U, Pu and Np co-recovery we set by MIXSET-X.

Oral presentation

Development of U and Pu co-processing process; Demonstration of U, Pu and Np co-recovery with centrifugal contactors

Kudo, Atsunari; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Sato, Takehiko; Fujimoto, Ikuo; Obu, Tomoyuki

no journal, , 

no abstracts in English

Oral presentation

Development of U and Pu co-recovery in Tokai Reprocessing Plant; Development of reprocessing process in Operation Testing Laboratory in TRP

Kudo, Atsunari; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Yanagibashi, Futoshi; Obu, Tomoyuki

no journal, , 

no abstracts in English

Oral presentation

Solidification and stabilization for Pu nitrate solution at TRP, 1; Confirmations for equipment and facilities soundness after The Great East Japan Earthquake, and emergency safety measures

Takahashi, Naoki; Nakamura, Yoshinobu; Obu, Tomoyuki; Samoto, Hirotaka; Namatame, Toshihiro; Hoshi, Takahiro; Kurabayashi, Kazuaki; Mukai, Yasunobu; Kimura, Yuichi; Kurita, Tsutomu

no journal, , 

no abstracts in English

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