Refine your search:     
Report No.
 - 
Search Results: Records 1-13 displayed on this page of 13
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Recovery of U-Pu alloy from MOX using a pyroprocess series

Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo; Usami, Tsuyoshi*; Yahagi, Noboru*; Kurata, Masaki*

Nuclear Technology, 162(2), p.118 - 123, 2008/05

 Times Cited Count:17 Percentile:72.99(Nuclear Science & Technology)

A series test of pyro-process was carried out to recover U-Pu alloy from MONJU MOX pellets. In the Li-reduction step, the reduction behavior of MOX was similar to that of UO$$_{2}$$. In the electrorefining step, the separation factor between U and Pu was 5.7 for the combination of reduced MOX anode and liquid cadmium cathode, which is almost comparable to the value in the previous studies. For the material balance, approximately 98% of U and 103% of Pu were detected in the electrodes or molten salt after the electrolysis with respect to the initial amounts in the anode or molten salt. Considering the analytical error of ICP-AES, these values are reasonable. The remained amount of U in the anode was slightly larger than that of Pu due to the re-oxidation. The U-Pu alloy ingot was successfully formed by distillation of Cd.

Journal Articles

Integrated experiments of electrometallurgical pyroprocessing with using plutonium oxide

Koyama, Tadafumi*; Hijikata, Takatoshi*; Usami, Tsuyoshi*; Inoue, Tadashi*; Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo; Myochin, Munetaka

Journal of Nuclear Science and Technology, 44(3), p.382 - 392, 2007/03

 Times Cited Count:24 Percentile:82.64(Nuclear Science & Technology)

Electrometallurgical pyroprocessing is a promising technology to realize actinide fuel cycle. Integrated experiments to demonstrate electrometallurgical pyroprocessing of plutonium oxide in continuous operation were carried out. In each test, 10 to 20 g of PuO$$_{2}$$ was reacted with Li reductant to form metal product. The reduction products were charged in the anode basket of the electrorefiner with LiCl-KCl-UCl$$_{3}$$ electrolyte. With using the anodes, deposition of uranium on the solid cathode was carried out, when PuCl$$_{3}$$ concentration was low. After Pu/U ratio in salt electrolyte was increased enough, plutonium and uranium were recovered simultaneously on the liquid cadmium cathode. By heating up the deposits for distillation of the salt and the cadmium, U metal or Pu-U alloyed metal were obtained as residues in the crucible. It was first result to demonstrate the recovery of metal actinides in the continuous operation of pyroprocessing of oxide fuels.

Journal Articles

Recovery test of metal product from oxide fuel by electrometallurgical pyroprocess

Kitawaki, Shininchi; Shinozaki, Tadahiro; Fukushima, Mineo; Hijikata, Takatoshi*; Usami, Tsuyoshi*; Koyama, Tadafumi*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10

Electrometallurgical pyroprocess is a key innovative technology to realize closed actinides cycle with keeping high proliferation-resistance and economy. JNC and CRIEPI have been carrying out the integrated tests of electrometallurgical reprocessing of metal and oxide Pu-containing fuel to demonstrate whole process in continuous operation. After intensive cold test to confirm the functions of experimental apparatus and the test conditions, recovery test of actinide metal product from actinide oxide fuels has started as a first series of the integrated tests. In this report, result of the recovery test is described to elucidate the material flow in the process.

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 12; Electrorefining test with reduced MOX

Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo; Usami, Tsuyoshi*; Yahagi, Noboru*; Kurata, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 11; Lithium reduction behavior of MOX pellet

Usami, Tsuyoshi*; Kurata, Masaki*; Yahagi, Noboru*; Kitawaki, Shinichi; Shinozaki, Tadahiro; Fukushima, Mineo

no journal, , 

no abstracts in English

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 13; Cd-distillation of cathode and formation of U-Pu alloy

Yahagi, Noboru*; Usami, Tsuyoshi*; Kurata, Masaki*; Kitawaki, Shinichi; Fukushima, Mineo; Shinozaki, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Demonstration test with plutonium for electrometallurgical pyroprocess at CPF, 14; Re-treatment of anode residue generated from electrorefining of reduced MOX

Kurata, Masaki*; Usami, Tsuyoshi*; Yahagi, Noboru*; Kitawaki, Shinichi; Fukushima, Mineo; Shinozaki, Tadahiro

no journal, , 

no abstracts in English

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 12; Reaction of simulated residue with nitric acid

Usami, Tsuyoshi*; Tsukada, Takeshi*; Morita, Yasuji

no journal, , 

Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. To evaluate characteristics of the insoluble residue, simulated residue of metal alloy composed of Ru, Rh, Pd, Mo and Re was dissolved with heated nitric acid. The results showed that higher concentration of Pd and Mo in the alloy makes the alloy easier to be dissolved. The alloy without Pd was hardly dissolved by nitric acid. On the other hand, the alloy without Ru was dissolved easily.

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 19; Dependence of dissolution rate of insoluble residue on its composition

Usami, Tsuyoshi*; Tsukada, Takeshi*; Yamagishi, Isao; Morita, Yasuji

no journal, , 

Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. To evaluate characteristics of the insoluble residue, simulated residue of metal alloy composed of Ru, Mo, Rh and Pd was dissolved with heated nitric acid. The results showed that higher concentration of Pd in the alloy makes the alloy easier to be dissolved, and higher concentration of Ru makes the alloy more difficult to be dissolved.

Oral presentation

Development of high-level liquid waste conditioning technology for advanced nuclear fuel cycle, 21; Overall results and evaluation

Morita, Yasuji; Yamagishi, Isao; Sato, Soichi; Kirishima, Akira*; Fujii, Toshiyuki*; Uehara, Akihiro*; Tsukada, Takeshi*; Usami, Tsuyoshi*; Kurosaki, Ken*

no journal, , 

Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. The present report gives the overall results of the research and development and their evaluation. For the Mo separation, the extraction process with HDEHP was developed by performing continuous extraction tests and process simulation by a calculation code. An extraction process for Pd by 5,8-diethyl-7-hydroxy-6-dodecanone oxime was also developed, but was evaluated as less mature than the HEDHP process. As Ru separation method, volatilization of RuO$$_{4}$$ after electrochemical oxidation was examined. Dissolution residue (metal alloy) and recovered Pd and Ru were solidified together by hot-press method.

Oral presentation

Long-term dissolution behavior of insoluble residue

Usami, Tsuyoshi*; Tsukada, Takeshi*; Morita, Yasuji

no journal, , 

Development of high-level liquid waste (HLW) conditioning technology for advanced nuclear fuel cycle was conducted for the purpose of the reduction of potential problems in the verification process for HLW. It includes development of separation technology for Mo, Pd and Ru from HLW and development of separate treatment of the insoluble residue. To evaluate characteristics of the insoluble residue, simulated residue of metal alloy composed of Ru, Rh, Pd, Mo and Re was dissolved with heated nitric acid. The results showed that higher concentration of Pd and Mo in the alloy makes the alloy easier to be dissolved. The alloy without Pd was hardly dissolved by nitric acid. On the other hand, the alloy without Ru was dissolved easily.

Oral presentation

Application of partitioning and transmutation technology to waste management; An Attempt to assess total performance of advanced nuclear fuel cycle, 4; A Trial assessment for MOX plu-thermal cycle

Makino, Hitoshi; Asano, Hidekazu*; Usami, Tsuyoshi*; Kanehira, Norio*; Ikeda, Takao*; Kawai, Kota*; Watanabe, Daisuke*

no journal, , 

This presentation shows current status of discussion on "A trial assessment for MOX plu-thermal cycle" which is a challenge as part of an attempt to assess total performance of advanced nuclear fuel cycle in the Research Committee on Disposal of Radioactive Waste and Partitioning-Transmutation Technology.

Oral presentation

Application of partitioning and transmutation technology to waste management; Assessment of total performance of advanced nuclear fuel cycle, 3; An Assessment for MOX plu-thermal cycle

Makino, Hitoshi; Asano, Hidekazu*; Usami, Tsuyoshi*; Tsukada, Takeshi*; Ikeda, Takao*; Kawai, Kota*; Watanabe, Daisuke*

no journal, , 

This presentation shows current status of discussion on "An assessment for MOX plu-thermal cycle" which is a challenge as part of an attempt to assess total performance of advanced nuclear fuel cycle in the Research Committee on Disposal of Radioactive Waste and Partitioning-Transmutation Technology.

13 (Records 1-13 displayed on this page)
  • 1