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Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro
JAERI-Tech 2005-039, 23 Pages, 2005/07
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 C. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests.
Kurosawa, Makoto; Ouchi, Shoichi*; Abe, Jiro; Okane, Shogo; Usui, Takeshi
JAERI-Tech 2002-036, 24 Pages, 2002/03
Method for measurement of plutonium in -waste using passive ray has been adopted at Plutonium Fuel Research Facility. Recently, research of neptunium has been started. It is necessary to evaluate the passive ray method for measurement of plutonium in -waste including plutonium and neptunium together. This report describes the results of comparing the two methods, deduction method and division method. The error of deduction method is about 10 to 15% when the quantity of plutonium is larger than 100 mg in the waste. But the error reaches more than 50% when the quantity of plutonium is less than 10 mg and the ratio of plutonium and neptunium is less than one. On the other hand, the error of division method is about a few to 15% when the quantity of plutonium is larger than 100 mg in the waste. The error is about 30 to 50% when the quantity of plutonium is less than 10 mg, but the error is not affected by the ratio of plutonium and neptunium. By reason of this results, the division method is adopted for measurement of plutonium in -waste including neptunium.
Nakahira, Masataka; Shibanuma, Kiyoshi; Kajiura, Soji*; Shibui, Masanao*; Koizumi, Koichi; Takeda, Nobukazu; Kakudate, Satoshi; Taguchi, Ko*; Oka, Kiyoshi; Obara, Kenjiro; et al.
JAERI-Tech 2002-029, 27 Pages, 2002/03
The ITER vacuum vessel (VV) R&D has progressed with the international collaborative efforts by the Japan, Russia and US Parties during the Engineering Design Activities (EDA). Fabrication and testing of a full-scale VV sector model and a port extension have yielded critical information on the fabrication and assembly technologies of the vacuum vessel, magnitude of welding distortions, dimensional accuracy and achievable tolerances during sector fabrication and field assembly. In particular, the dimensional tolerances of 3 mm for VV sector fabrication and 10 mm for VV sector field assembly have been achieved and satisfied the requirements of 5 mm and 20 mm, respectively. Also, the basic feasibility of the remote welding robot has been demonstrated. This report presents detailed fabrication and assembly technologies such as welding technology applicable to the thick wall without large distortion, field joint welding technology between sectors and remote welding technology through the VV R&D project.
Ouchi, Shoichi*; Kurosawa, Makoto; Abe, Jiro; Okane, Shogo; Usui, Takeshi
JAERI-Tech 2002-026, 35 Pages, 2002/03
Both gloveboxes No.801-W for measuring samples of uranium or plutonium and No.802-W for analyzing the quantity of uranium or plutonium are established at twenty five years ago in the analyzing room No.108 of Plutonium Fuel Research Facility. It was planned to scrap the gloveboxes and to establish new gloveboxes. This report describes the technical view of the scrapping works.
Hiroki, Seiji; Abe, Tetsuya; Obara, Kenjiro; Murakami, Yoshio
J. Vac. Sci. Technol., A, 9(1), p.154 - 157, 1991/01
no abstracts in English
Sakurai, Satoshi; Hirata, Masaru; ; Usuda, Shigekazu; Abe, Jiro; ; Tachimori, Shoichi; ; Kurihara, Masayoshi; Kobayashi, Iwao
JAERI-M 90-059, 35 Pages, 1990/03
no abstracts in English
Obara, Kenjiro; Abe, Tetsuya; Murakami, Yoshio
JAERI-M 87-143, 66 Pages, 1987/09
no abstracts in English
; ; ;
Shinku, 29(6), p.245 - 250, 1986/00
no abstracts in English
; Murakami, Yoshio; ; Hiroki, S.; ; *; *; *
Journal of Nuclear Materials, 133-134, p.754 - 759, 1985/00
Times Cited Count:16 Percentile:85.27(Materials Science, Multidisciplinary)no abstracts in English
; Abe, Jiro; ;
Journal of Nuclear Science and Technology, 22(8), p.669 - 677, 1985/00
Times Cited Count:1 Percentile:24.15(Nuclear Science & Technology)no abstracts in English
Hiroki, S.; *; ; ; ; Murakami, Yoshio
Shinku, 28(5), p.300 - 303, 1985/00
no abstracts in English
*; ; Hiroki, S.; ; Murakami, Yoshio
JAERI-M 84-105, 51 Pages, 1984/06
no abstracts in English
Hiroki, S.; ; *; ; Murakami, Yoshio
JAERI-M 84-012, 14 Pages, 1984/02
no abstracts in English
Murakami, Yoshio; ; ;
J.Vac.Sci.Tecnol.,A, 2(4), p.1589 - 1592, 1984/00
no abstracts in English
; ; Hiroki, S.; ; Murakami, Yoshio
Shinku, 27(5), p.339 - 342, 1984/00
no abstracts in English
Hiroki, S.; ; *; ; ; Murakami, Yoshio
Shinku, 27(5), p.386 - 388, 1984/00
no abstracts in English
; Murakami, Yoshio; ; Hiroki, S.; ; *; *; *; *
Shinku, 27(5), p.394 - 397, 1984/00
no abstracts in English
; ; ; ;
JAERI-M 83-087, 16 Pages, 1983/06
no abstracts in English
*; ; ; Hiroki, S.; Murakami, Yoshio
Shinku, 26(5), p.494 - 498, 1983/00
no abstracts in English
; *; ; Hiroki, S.; Murakami, Yoshio
Shinku, 26(5), p.488 - 493, 1983/00
no abstracts in English