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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.

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.

Journal Articles

In-pile and post-irradiation creep of type 304 stainless steel under different neutron spectra

Kurata, Yuji; Itabashi, Yukio; Mimura, Hideaki*; Kikuchi, Taiji; Amezawa, Hiroo; Shimakawa, Satoshi; Tsuji, Hirokazu; Shindo, Masami

Journal of Nuclear Materials, 283-287(Part.1), p.386 - 390, 2000/12

 Times Cited Count:5 Percentile:38.4(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Effect of helium to dpa ratio on fatigue behavior of austenitic stainless steel irradiated to 2 dpa

Ioka, Ikuo; Yonekawa, Minoru; Miwa, Yukio; Mimura, Hideaki; Tsuji, Hirokazu; Hoshiya, Taiji

Journal of Nuclear Materials, 283-287(Part.1), p.440 - 445, 2000/12

 Times Cited Count:7 Percentile:47.79(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Post irradiation mechanical properties of type 304 stainless steel

Tsuji, Hirokazu; ; Miwa, Yukio; Itabashi, Yukio; *; Shimakawa, Satoshi; Mimura, Hideaki; ; ; Tsukada, Takashi; et al.

Advances in Science and Technology, 24, p.483 - 490, 1999/00

no abstracts in English

Journal Articles

Properties of precipitation hardened steel irradiated at 323K in the Japan Materials Testing Reactor

Niimi, Motoji; Matsui, Yoshinori; Jitsukawa, Shiro; Hoshiya, Taiji; Tsukada, Takashi; Omi, Masao; Mimura, Hideaki; Ooka, Norikazu; *

Journal of Nuclear Materials, 271-272, p.92 - 96, 1999/00

 Times Cited Count:4 Percentile:35.68(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Post-irradiation fatigue test of 21/4Cr-1Mo steel for the pressure vessel material of the HTTR

; Fukaya, Kiyoshi; Nishiyama, Yutaka; Suzuki, Masahide; Eto, Motokuni; Omi, Masao; Mimura, Hideaki; Ooka, Norikazu

JAERI-Research 96-028, 33 Pages, 1996/06

JAERI-Research-96-028.pdf:1.85MB

no abstracts in English

JAEA Reports

Development of a remote controlled fatigue testing apparatus at elevated temperature in controlled environment

Omi, Masao; Mimura, Hideaki; ; Fukaya, Kiyoshi; Yonekawa, Minoru; Goto, Ichiro; ; Saito, Junichi; Eto, Motokuni;

JAERI-Tech 96-005, 39 Pages, 1996/02

JAERI-Tech-96-005.pdf:2.28MB

no abstracts in English

JAEA Reports

Pre-pulse irradiation examination, NSRR pulse irradiation and post-pulse irradiation examination of MH-2 fuel rod

Yanagisawa, Kazuaki; Katanishi, Shoji; *; Sasajima, Hideo; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.

JAERI-M 92-015, 211 Pages, 1992/02

JAERI-M-92-015.pdf:8.77MB

no abstracts in English

JAEA Reports

Pre-pulse irradiation examination, NSRR pulse irradiation and post-pulse irraditaiton examination of MH-1 fuel rod

Yanagisawa, Kazuaki; Sasajima, Hideo; Katanishi, Shoji; *; ; Horiki, Oichiro; Mimura, Hideaki; ; ; ; et al.

JAERI-M 91-220, 186 Pages, 1992/01

JAERI-M-91-220.pdf:7.02MB

no abstracts in English

JAEA Reports

Post irradiation examination of 14 $$times$$ 14 PWR type fuel rod prior to pulse irradiation in NSRR

Yanagisawa, Kazuaki; Sasajima, Hideo; Katanishi, Shoji; ; ; Nihei, Yasuo; Mimura, Hideaki; ; Yamahara, Takeshi; *

JAERI-M 91-218, 199 Pages, 1992/01

JAERI-M-91-218.pdf:15.05MB

no abstracts in English

JAEA Reports

Behavior of plutonium and fission products in irradiated mixed carbide fuel

; Maeda, Atsushi; Iwai, Takashi; Kanazawa, Hiroyuki; Mimura, Hideaki; Arai, Yasuo

JAERI-M 91-192, 25 Pages, 1991/11

JAERI-M-91-192.pdf:1.35MB

no abstracts in English

JAEA Reports

Technical report: Technical development on silicide plate-type fuel experiment at Nuclear Safety Research Reactor

Yanagisawa, Kazuaki; Soyama, Kazuhiko; Ichikawa, Hiroki; ; Hoshino, Osamu; ; ; ; Kanazawa, Hiroyuki; Kimura, Yasuhiko; et al.

JAERI-M 91-114, 67 Pages, 1991/08

JAERI-M-91-114.pdf:4.28MB

no abstracts in English

JAEA Reports

Study on behavior of niobia dopant UO$$_{2}$$ fuel under reactivity initiated accident conditions

Yanagisawa, Kazuaki; Mimura, Hideaki; Kimura, Yasuhiko

JAERI-M 90-164, 64 Pages, 1990/09

JAERI-M-90-164.pdf:4.96MB

no abstracts in English

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