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Journal Articles

Fabrication of U-Pu-Zr metallic fuel elements for the irradiation test at experimental fast test reactor Joyo

Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.245 - 256, 2011/12

Sodium-bonded metallic fuel elements were fabricated for the first time in Japan for the irradiation test in the experimental fast test reactor JOYO. U-20Pu-10Zr fuel slugs of 200 mm in length and approximately 5 mm in diameter were fabricated in a small-scale injection casting furnace. Each fuel slug was loaded into the ferritic martenstic stainless steel (PNC-FMS) cladding tube with the sodium thermal bond, thermal insulator and reflector in a helium gas atmosphere glove box. After top-end plug welding to the cladding tube and heat treatment of the welding area, each fuel element was subjected to the sodium bonding process. After the inspection such as element length, gas plenum length and helium-leak tightness, six metallic fuel elements are transported to the JOYO site for the coming irradiation test.

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.

Oral presentation

Fabrication of metallic fuel for irradiation test at JOYO, 4; Fabrication of metallic fuel elements

Nakamura, Kinya*; Kikuchi, Hironobu; Ogata, Takanari*; Iwai, Takashi; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori

no journal, , 

Irradiation test of metallic fuel at fast test reactor JOYO is planned. By using techniques of casting, fabrication, analysis and inspection, metallic fuel elements were made for the first time in Japan. In this paper, fabrication technique of metallic fuel elements is reported. After filling up thermal bond (Na), a reflector element, a thermal shelter element and a fuel slug, the upper plug was welded. Sodium bonding treatment was carried out by vibrating the fuel element under heating. By inspection, it was confirmed that the specifications were satisfied.

Oral presentation

Fabrication of metallic fuel elements for irradiation test at JOYO, 3, Fabrication of metallic fuel elements

Nakamura, Kinya*; Kikuchi, Hironobu; Ogata, Takanari*; Iwai, Takashi; Arai, Yasuo; Uozumi, Koichi*; Hijikata, Takatoshi*; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori

no journal, , 

Irradiation test of metallic fuel elements at fast test reactor JOYO is planned. By the development of fabrication technique of casting, structure, analysis and inspection, metallic fuel elements were fabricated. In this paper, the structure technique is reported. Thermal bond (Na), element insulator and fuel slug were filled in PNC-FMS cladding, and upper plug was welded. Sodium bonding treatment was performed by shaking the fuel element under heating. By inspection, it was confirmed that the specification were satisfied.

Oral presentation

Development of stable solidification technique of ALPS sediment wastes by apatite ceramics, 1; General plan

Takeshita, Kenji*; Nakase, Masahiko*; Kanagawa, Shun*; Hijikata, Takatoshi*; Koma, Yoshikazu

no journal, , 

no abstracts in English

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 27; Cesium volatilization from used inorganic absorbents

Uruga, Kazuyoshi*; Furukawa, Shizue*; Hijikata, Takatoshi*; Koyama, Tadafumi*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

no abstracts in English

Oral presentation

Development of stable solidification technique of ALPS sediment wastes by apatite ceramics, 10; Characteristics of hydrogen gas generation from solidified apatite

Kato, Jun; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Koma, Yoshikazu; Nakase, Masahiko*; Utsumi, Kazuo*; Takeshita, Kenji*; Kanagawa, Shun*; Hijikata, Takatoshi*

no journal, , 

no abstracts in English

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