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Journal Articles

Establishment of technological basis for fabrication of U-Pu-Zr ternary alloy fuel pins for irradiation tests in Japan

Kikuchi, Hironobu; Nakamura, Kinya*; Iwai, Takashi; Nakajima, Kunihisa; Arai, Yasuo; Ogata, Takanari*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.323 - 331, 2011/12

A high-purity Ar gas atmosphere glovebox accommodating injection casting and sodium-bonding apparatuses was newly installed in Plutonium Fuel Research Facility (PFRF) of Oarai Research and Development Center, Japan Atomic Energy Agency. Past experiences in PFRF led to the establishment of technological basis of fabrication of U-Pu-Zr alloy fuel pin for the first time in Japan. After the injection casting of U-Pu-Zr alloy, the metallic fuel pins are fabricated by welding upper- and lower end plugs with cladding tube of ferritic-martensitic steel. Subsequent to the sodium bonding for filling the annular gap region between the U-Pu-Zr alloy and cladding tube with the melted sodium, the fuel pins are subjected to the inspection for irradiation tests. This paper summarizes the equipment of the apparatuses and the technological basis for fabrication of U-Pu-Zr alloy fuel pins for the coming irradiation test in the experimental fast test reactor JOYO.

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

Fabrication of U-Pu-Zr metallic fuel elements for irradiation test at Joyo

Nakamura, Kinya*; Ogata, Takanari*; Kikuchi, Hironobu; Iwai, Takashi; Nakajima, Kunihisa; Kato, Tetsuya*; Arai, Yasuo; Koyama, Tadafumi*; Itagaki, Wataru; Soga, Tomonori; et al.

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12

CRIEPI and JAEA have fabricated sodium-bonded metallic fuel elements for the first time in Japan as a collaborative research, for use in the irradiation test at the experimental fast test reactor Joyo. The irradiation test aims to assess the irradiation behavior of the fuel and the internal wastage of the stainless-steel cladding by rare-earth fission products at a maximum cladding temperature above 873 K. U-20 wt% Pu-10 wt% Zr alloy fuel slugs of 200 mm length were fabricated in an injection-casting furnace using U metal, U-Pu alloy and Zr metal. Two types of fuel slug were fabricated, i.e., 5.05 mm and 4.95 mm in diameter, and loaded into a ferritic-martensitic stainless-steel cladding tubes, respectively. After top-end-plug welding to the cladding tube, each fuel element was subjected to sodium bonding to fill the annular gap between the fuel slug and the cladding with melted sodium. The fabrication results indicated that the characteristics of the fuel elements were within the required specifications.

JAEA Reports

Scrapping work of glovebox 702-D for plutonium fuels

Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo

JAEA-Technology 2009-055, 35 Pages, 2009/11

JAEA-Technology-2009-055.pdf:8.29MB

Glovebox 702-D for electron probe micro-analysis for plutonium fuels was installed about thirty years ago in the room 107 of Plutonium Fuel Research Facility(PFRF) in Oarai Research Establishment of former Japan Atomic Energy Research Institute(JAERI). The glovebox was scrapped for replacing the old-type electron probe micro-analyzer by a new-type scanning electron microscope. This report summarizes the scrapping work of the glovebox from the technical viewpoints.

JAEA Reports

Welding of metallic fuel elements for the irradiation test in JOYO; Preliminary tests and welding execution tests (Joint research)

Kikuchi, Hironobu; Nakamura, Kinya*; Iwai, Takashi; Arai, Yasuo

JAEA-Technology 2009-049, 22 Pages, 2009/10

JAEA-Technology-2009-049.pdf:13.99MB

Irradiation tests of metallic fuels elements in fast test reactor JOYO are planned under the joint research of Japan Atomic Energy Agency (JAEA) and Central Research Institute of Electric Power Industry (CRIEPI). Six U-Pu-Zr fuel elements clad with ferritic martensitic steel are fabricated in Plutonium Fuel Research Facility (PFRF) of JAEA-Oarai for the first time in Japan. In PFRF, the procedures of fabrication of the fuel elements were determined and the test runs of the equipments were carried out before the welding execution tests for the fuel elements. Test samples for confirming the welding condition between the cladding tube and top and bottom endplugs were prepared, and various test runs were carried out before the welding execution tests. As a result, the welding conditions were finalized by passing the welding execution tests.

Journal Articles

Scrapping work of gloveboxes in plutonium fuel research facility

Iwai, Takashi; Kikuchi, Hironobu; Arai, Yasuo

Dekomisshoningu Giho, (36), p.54 - 63, 2007/10

Both gloveboxes No.121-D and No.122-D used for metallography were installed about thirty years ago in the room No.101 of Plutonium Fuel Research Facility in Oarai Research Esbtablishment of former Japan Atomic Energy Research Institute (JAERI). It was planned to scrap the old gloveboxes and build new ones for starting new research on advanced fuel. This report summarized the scrapping work of the gloveboxes from the technical viewpoints.

JAEA Reports

Post-irradiation examinations of inert matrix nitride fuel irradiated in JMTR (01F-51A capsule)

Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Honda, Junichi; Hatakeyama, Yuichi; Ono, Katsuto; Matsui, Hiroki; Arai, Yasuo

JAEA-Research 2007-026, 75 Pages, 2007/03

JAEA-Research-2007-026.pdf:13.6MB

A plutonium nitiride fuel pin containing inert matrix such as ZrN and TiN was encapsuled in 01F-51A and irradiated in JMTR. Minor actinides are surrogated by plutonium. Average linear powers and burnups were 408W/cm, 30000MWd/t(Zr+Pu)(132000MWd/t-Pu) for (Zr,Pu)N and 355W/cm, 38000MWd/t(Ti+Pu)(153000MWd/t-Pu) for (TiN,PuN). The irradiated capsule was transported to Reactor Fuel Examination Facility and subjected to non-destructive and destructive post irradiation examinations. Any failure was not observed in theirradiated fuel pin. Very low fission gas release rate of about 1.6% was measured. The inner surface of cladding tube did not show any signs of chemical interaction with fuel pellets.

JAEA Reports

Scrapping work of gloveboxes No.121-D and No.122-D

Iwai, Takashi; Kikuchi, Hironobu; Arai, Yasuo

JAEA-Technology 2006-009, 31 Pages, 2006/03

JAEA-Technology-2006-009.pdf:4.61MB

Both gloveboxes No.121-D and No.122-D for metallography were installed twenty seven years ago in the room No.101 of Plutonium Fuel Research Facility in Oarai Research Establishment of former Japan Atomic Energy Research Institute (JAERI). It was planed to scrap the old gloveboxes and build new ones for starting new research on advanced fuel. This report summarizes the scrapping work of the gloveboxes from the technical viewpoints.

JAEA Reports

Fabrication of inert-matrix nitride fuel pins for the irradiation test at JMTR

Nakajima, Kunihisa; Iwai, Takashi; Kikuchi, Hironobu; Serizawa, Hiroyuki; Arai, Yasuo

JAERI-Research 2005-027, 42 Pages, 2005/09

JAERI-Research-2005-027.pdf:4.15MB

Nitride fuel pins containing inert matrix such as ZrN and TiN were fabricated for the irradiation test at JMTR, aiming at understanding irradiation behavior of nitride fuel for transmutation of minor actinides. Minor actinides are surrogated by plutonium in the present fuel pin. This report describes the preparation and characterization of fuel pellets, and fabrication of fuel pins. The irradiation for 11 cycles from May 2002 to November 2004 at JMTR was completed without any failure of fuel pins.

JAEA Reports

Design and installation of high-temperature ultrasonic measuring system and grinder for nuclear fuel containing trans-uranium elements

Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro

JAERI-Tech 2005-039, 23 Pages, 2005/07

JAERI-Tech-2005-039.pdf:2.89MB

A high-temperature ultrasonic measuring system had been designed and installed in a glovebox (711-DGB) to study a mechanical property of nuclear fuel containing trans-uranium (TRU) elements. A figuration apparatus for the cylinder-type sample preparation had also been modified and installed in an established glovebox (142-D). The system consists of an ultrasonic probe, a heating furnace, cooling water-circulating system, a cooling air compressor, vacuum system, gas supplying system and control system. An A/D converter board and an pulsar/Receiver board for the measurement of wave velocity were installed in a personal computer. The apparatus was modified to install into the glovebox. Some safety functions were supplied to the control system. The shape and size of the sample was revised to minimize the amount of TRU elements for the use of the measurement. The maximum sample temperature is 1500 $$^{circ}$$C. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests.

JAEA Reports

Post irradiation examination of (U,Pu)C and (U,Pu)N fuels for fast reactors; Destructive examination result of the fuel pins (Joint research)

Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Nagashima, Hisao; Kimura, Yasuhiko; Matsui, Hiroki; Arai, Yasuo

JAERI-Research 2002-038, 69 Pages, 2003/01

JAERI-Research-2002-038.pdf:12.46MB

Uranium-plutonium mixed carbide and nitiride fuel pins were fabricated in JAERI and irradiated at fast test rector JOYO based on the JAERI-JNC joint research program. The results of non-destructive and destructive post irradiation examinations cariied out at JNC were reported elsewhere. This report summarizes the results of destructive post irradiation examinations of (U,Pu)C and (U,Pu)N fuel pins carried out at JAERI.

JAEA Reports

Post-irradiation examinations of uranium-plutonium mixed nitride fuel irradiated in JMTR; 89F-3A capsule

Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Kimura, Yasuhiko; Nagashima, Hisao; Sekita, Noriaki; Arai, Yasuo

JAERI-Research 2000-010, p.110 - 0, 2000/03

JAERI-Research-2000-010.pdf:20.61MB

no abstracts in English

JAEA Reports

Behavior of actinides and fission products in mixed nitride fuels irradiated in JMTR; 88F-5A capsule

Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Kimura, Yasuhiko; Kanaitsuka, Fumio; Sekita, Noriaki; Arai, Yasuo

JAERI-Research 2000-009, p.36 - 0, 2000/03

JAERI-Research-2000-009.pdf:6.16MB

no abstracts in English

JAEA Reports

Irradiation experiments of the 13th-15th OGL-1 fuel assemblies

Hayashi, Kimio; Sawa, Kazuhiro; Shiratori, Tetsuo; Kikuchi, Hironobu; Fukuda, Kosaku; Kitajima, Toshio; Ito, Tadaharu; Waragai, Hyota

JAERI-Research 2000-001, p.116 - 0, 2000/01

JAERI-Research-2000-001.pdf:21.78MB

no abstracts in English

Journal Articles

Radiation damage in UO$$_{2}$$ bombarded with iodine and nickel ions at energies around 100 MeV

Hayashi, Kimio; ; Fukuda, Kosaku

Advances in Science and Technology, 24, p.439 - 446, 1999/00

no abstracts in English

JAEA Reports

Development of advanced fabrication technology for high-temperature gas-cooled reactor fuel; Reduction of coating failure fraction

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; Yoshimuta, Shigeharu*; *; *; *; *

JAERI-Research 98-070, 25 Pages, 1998/11

JAERI-Research-98-070.pdf:2.18MB

no abstracts in English

JAEA Reports

Design and installation of high-temperature X-ray diffractometer for transuranium elements and its performance test (Joint research)

Arai, Yasuo; Nakajima, Kunihisa; Serizawa, Hiroyuki; ; Suzuki, Yasufumi; Inoue, Tadashi*

JAERI-Tech 98-022, 21 Pages, 1998/06

JAERI-Tech-98-022.pdf:1.07MB

no abstracts in English

Journal Articles

Improvements in quality of as-manufactured fuels for high-temperature gas-cooled reactors

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; *; *; *; *

Journal of Nuclear Science and Technology, 34(3), p.325 - 333, 1997/03

 Times Cited Count:16 Percentile:75.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Radiation damage of UO$$_{2}$$ by high-energy heavy ions

Hayashi, Kimio; ; Fukuda, Kosaku

Journal of Nuclear Materials, 248, p.191 - 195, 1997/00

 Times Cited Count:21 Percentile:82.22(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Preirradiation characterization of HTGR fuel for HRB-22 capsule irradiation test; JAERI/USDOE collaborative irradiation test for HTGR fuel

Minato, Kazuo; ; Sawa, Kazuhiro; Tobita, Tsutomu; Fukuda, Kosaku

JAERI-Tech 95-056, 45 Pages, 1996/01

JAERI-Tech-95-056.pdf:3.02MB

no abstracts in English

34 (Records 1-20 displayed on this page)