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JAEA Reports

Plan and reports of coupled irradiation (JRR-3 and JOYO of research reactors) and hot facilities work (WASTEF, JMTR-HL, MMF and FMF); R&D project on irradiation damage management technology for structural materials of long-life nuclear plant

Matsui, Yoshinori; Takahashi, Hiroyuki; Yamamoto, Masaya; Nakata, Masahito; Yoshitake, Tsunemitsu; Abe, Kazuyuki; Yoshikawa, Katsunori; Iwamatsu, Shigemi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; et al.

JAEA-Technology 2009-072, 144 Pages, 2010/03

JAEA-Technology-2009-072.pdf:45.01MB

"R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant" was carried out from FY2006 in a fund of a trust enterprise of the Ministry of Education, Culture, Sports, Science and Technology. The coupled irradiations or single irradiation by JOYO fast reactor and JRR-3 thermal reactor were performed for about two years. The irradiation specimens are very important materials to establish of "Evaluation of Irradiation Damage Indicator" in this research. For the acquisition of the examination specimens irradiated by the JOYO and JRR-3, we summarized about the overall plan, the work process and the results for the study to utilize these reactors and some facilities of hot laboratory (WASTEF, JMTR-HL, MMF and FMF) of the Oarai Research-and-Development Center and the Nuclear Science Research Institute in the Japan Atomic Energy Agency.

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:16 Percentile:74.37(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:22 Percentile:81.84(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.

Journal Articles

XAFS studies of uranium(VI) and thorium(IV)-amide and TBP complexes in ethanol solution

Yaita, Tsuyoshi; Narita, Hirokazu*; Suzuki, Shinichi; Shiwaku, Hideaki; Motohashi, Haruhiko; Ono, Hideo; Usami, Noriko*; Kobayashi, Katsumi*

Photon Factory Activity Report 1997, P. 81, 1997/00

no abstracts in English

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

R&D project on irradiation damage management technology for structural materials of long-life nuclear plant, 2; Plan and execution of coupling irradiation (JRR-3 and JOYO) and Hot facilities work (WASTEF, JMTR-HL, MMF and FMF)

Matsui, Yoshinori; Nabeya, Hideaki; Kusunoki, Tsuyoshi; Takahashi, Hiroyuki; Aizawa, Masao; Nakata, Masahito; Numata, Masami; Usami, Koji; Endo, Shinya; Ito, Kazuhiro; et al.

no journal, , 

We are proceeding with the study of "R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant". For the study, it is important that the irradiated specimens are gotten by the coupling of JRR-3 and JOYO. This reports the total irradiation plan in the study, and the executed work for the coupling irradiation (JRR-3 and JOYO) including the Hot facilities work of Tokai and Oarai in the 2006 fiscal year.

Oral presentation

Development of reactivity feedback effect measurement techniques under sub-critical condition in fast reactor, 1-1; Purpose and program

Okajima, Shigeaki; Nishi, Hiroshi; Yamane, Yoshihiro*; Kanemoto, Shigeru*; Yamane, Tsuyoshi; Mori, Takamasa; Kitamura, Yasunori; Fukushima, Masahiro; Kitano, Akihiro; Ando, Masaki; et al.

no journal, , 

The program was planned and has been carried out to develop of the reactivity feedback effect measurement techniques under sub-critical condition in the start-up experiment for fast reactors. The program includes the demonstration of the developed technique in fast critical assembly (FCA) and the proposal of the appropriate measurement system based on the results. The background and the purposes of the program and the outline of development subjects are presented.

Oral presentation

Facility of radioactive materials beamline at KEK

Hirao, Norie; Baba, Yuji; Sekiguchi, Tetsuhiro; Shimoyama, Iwao; Okamoto, Yoshihiro; Suzuki, Shinichi; Yaita, Tsuyoshi; Usami, Noriko*; Kobayashi, Katsumi*

no journal, , 

We report here the facility of radioactive materials beamline at KEK (High Energy Accelerator Research Organization). The beamline was designed and built by Japan Atomic Energy Agency (JAEA). The experimental stations of BL-27 are located inside the "hot" laboratory where radioactive materials or samples including U or Th can be handled, in order to irradiate these samples with synchrotron X-rays. The beamline is divided into two branch lines; one is BL-27A for soft X-rays (1.8 to 6 keV) and the other is BL-27B for X-rays (4 to 20 keV). In BL-27A, irradiation apparatuses for radiobiology, photoelectron spectrometer (XPS) and photoelectron emission microscopy (PEEM) are installed in tandem. In BL-27B, irradiation apparatuses for radiobiology and XAFS spectrometer are inside hatch. This beamline is equipped with XAFS experiments (transmission XAFS, fluorescent XAFS and Imaging XAFS).

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.

18 (Records 1-18 displayed on this page)
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