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Saito, Junichi; Kobayashi, Yohei*; Shibutani, Hideo*
Materials Transactions, 62(10), p.1524 - 1532, 2021/10
Times Cited Count：5 Percentile：41.35(Materials Science, Multidisciplinary)no abstracts in English
Saito, Junichi; Kobayashi, Yohei*; Shibutani, Hideo*
Nihon Kinzoku Gakkai-Shi, 85(3), p.110 - 119, 2021/03
Times Cited Count：1 Percentile：8.06(Metallurgy & Metallurgical Engineering)Kobayashi, Takanori; Sakon, Miyoji; Takada, Osamu; Hatori, Masakazu; Sakamoto, Tsutomu; Sato, Toshiyuki; Kazama, Akihito*; Ishizawa, Yoshihiro*; Igawa, Katsuhisa*; Nakae, Hideo*
JAEA-Review 2011-047, 48 Pages, 2012/02
JAEA-Review-2011-047.pdf:9.58MB
I confirmed a leak of the effluent gas from cylinder part during a load examination after the check of the emergency generator C unit on December 28, 2010 of the facilities check average and confirmed crack in No.8 cylinder liner part. As a result, because it was not performed oil pressure management properly without attaching an oil pressure gauge when I removed cylinder liner about the cause, crack occurred by having been able to write excessive stress for the cylinder liner and reached damage. By a process of this investigation, a fall of the materials strength of some cylinder liner was confirmed, but because a lead ingredient got mixed with materials by a casting process at the time of the production of the cylinder liner, as for this, Widmannst tten graphite occurred, and it became clear that materials strength fell. In addition, I performed inspection by the supersonic wave velocity measurement as technique to distinguish this Widmannst tten graphite easily and confirmed that I was effective.
Kikuchi, Masamitsu; Taki, Mitsumasa; Kume, Etsuo; Kobayashi, Hideo*; Yamada, Toshio*; Yamaguchi, Takenori
JAERI-Data/Code 2004-006, 146 Pages, 2004/03
JAERI-Data-Code-2004-006.pdf:6.87MB
The nuclear facilities, which are required to control the released radioactive gases and liquid, exist in Tokai research establishment as much as 40. These radioactive controls are carried out complying with the statutes in each facility. The released radioactivity data of each facility must be reported to MEXT and Ibaraki Prefecture from Tokai Research Establishment. This system is developed to make the database gathering the radioactivity data of each facilities for unitary control as Tokai Research Establishment and contribute to make the reports to MEXT and Ibaraki Prefecture.
Hosotani, Risa; Sato, Naomitsu*; Shimizu, Takehiko; KOBAYASHI, Hideo
Saikuru Kiko Giho, (25), p.25 - 32, 2004/00
To observe the airborne gamma radiation dose rate, monitoring posts are set up to a border of supervised area of JNC-OEC. Measurement values of some ionization chambers set at monitoring posts were increased by unknown origin signal at random times. To probe the cause, measurement of electric field intensity at the ionization chamber and immunity test at anechoic chamber are carry out. Result of examination made clear that measurement values are increased by specific frequency band electromagnetic wave. They were also clearly that ferrite cores and shield tube are effective as eliminate of an electromagnetic wave noise. When ferrite cores are attached to cables of ionization chambers, unknown increase of measurement value doesn't occur.
Taki, Mitsumasa; Kikuchi, Masamitsu; Kobayashi, Hideo*; Yamaguchi, Takenori
JAERI-Data/Code 2003-006, 99 Pages, 2003/05
JAERI-Data-Code-2003-006.pdf:6.97MB
A computer code (EDAS) was developed to assess the public dose for the safety assessment to get the license of nuclear reactor operation. This code system is used for the safety analysis of public around the nuclear reactor in case of normal operation and severe accident. This code was revised and composed for personal computer user according to the Nuclear Safety Guidelines reflected the ICRP1990 recommendation. These guidelines are revised by Nuclear Safety Commission on March, 2001, which are “Weather analysis guideline for the safety assessment of nuclear power reactor", “ Public dose around the facility assessment guideline corresponding to the objective value for nuclear power light water reactor" and “Public dose assessment guideline for safety review of nuclear power light water reactor". This code has been already opened for public user by JAERI, and English version code and user manual are prepared moreover. This English version code is helpful for international cooperation concerning the nuclear safety assessment with JAERI.
Kobayashi, Hideo
Genshiryoku Nenkan 2001/2002-Nen Ban, p.103 - 105, 2001/11
no abstracts in English
; Kobayashi, Hideo
JAERI-M 93-036, 51 Pages, 1993/03
no abstracts in English
; Kobayashi, Hideo
Proc. of Asia Congress on Radiation Protection, p.199 - 202, 1993/00
no abstracts in English
S.J.Hu*; ; Kobayashi, Hideo
Health Physics, 61(6), p.831 - 835, 1991/12
Times Cited Count：2 Percentile：31.89(Environmental Sciences)no abstracts in English
Taki, Mitsumasa; Kobayashi, Hideo; Suzuki, Takashi; Shimizu, Isamu
JAERI-M 90-206, 345 Pages, 1990/11
no abstracts in English
S.J.Hu*; ; Kobayashi, Hideo
JAERI-M 89-041, 49 Pages, 1989/04
no abstracts in English
Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; ; Kobayashi, Hideo
JAERI-M 88-218, 124 Pages, 1988/11
no abstracts in English
1982); ; ; ;
JAERI-M 83-201, 40 Pages, 1983/11
no abstracts in English
; ; ; ;
JAERI-M 83-071, 130 Pages, 1983/05
no abstracts in English
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JAERI-M 82-021, 292 Pages, 1982/03
no abstracts in English
; ; ; ;
JAERI-M 9578, 19 Pages, 1981/07
no abstracts in English
; ; ;
JAERI-M 9128, 129 Pages, 1980/10
no abstracts in English
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JAERI-M 8856, 130 Pages, 1980/05
no abstracts in English
*; *; *; *; *; *; Imazu, Akira
PNC TN941 77-172, 44 Pages, 1977/10
This paper presents the cooperative work by PNC PNC and CRIEPI on the AE application to a creep-fatigue test of a Type 304 long elbow test assembly, that is, almost the 1/2-scale model of the primary coolant piping component of the proto-type FBR "MONJU". The creep-fatigue test was performed in air at 600
C with the displacement-controlled in-plane bending load. AE characteristics, such as ring-down count rates, signal waveforms, peak-amplitude distributios and signal location patterns, were analysed in the process of the stationary creep-fatigue loading and the special loading for evaluating the effectiveness of AET to detect the piping detects.
