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JAEA Reports

Report on investigation of cause of crack at instrumentation pipe in JMTR; Results of vibration and stress analysis

Hanawa, Satoshi; Tachibana, Yukio; Iyoku, Tatsuo; Ishihara, Masahiro; Ito, Haruhiko

JAERI-Tech 2003-064, 25 Pages, 2003/07

JAERI-Tech-2003-064.pdf:2.84MB

On the 147cycle operation, the water leakage was found at the pressure instrumentation pipe which is attached to the exit pipe of No.1 charge pump of the purification system of primary cooling system at JMTR in the Oarai establishment, JAERI. Then JMTR was shutted down manually on December 10th. It was predicted that the crack on the pressure instrumentation pipe was initiated and propagated by the cyclic load which was caused by the charge pump. Therefore, vibration and stress analyses of pressure instrumentation pipe were performed. From the vibration analysis, the natural frequency of the pressure instrumentation pipe of No.1 charge pump is between 53$$sim$$58Hz, which is close to the resonance frequency of 50Hz. From the stress analysis results, total stress generated on the pressure instrumentation pipe is 112.2MPa at the natural frequency of 53Hz and 74.2Mpa at 58Hz. It was found that the stress of 112.2MPa is close to the fatigue limit of used materials.

JAEA Reports

Report on investigation of cause of crack at instrumentation pipe in JMTR; Data book on examination of pressure instrumentation pipe at JMTR hot laboratory

Working Group for Investigation of Cause of Crack Initiation

JAERI-Tech 2003-060, 183 Pages, 2003/07

JAERI-Tech-2003-060.pdf:55.37MB

On December 10, 2002, the water leakage was found at the pressure instrumentation pipe attached to the exit pipe of No.1 charging pump of the purification system of a primary cooling system at JMTR, and the cracks were detected on the pressure instrumentation pipe by the visual observation. The Investigation Committee for Water Leakage from Instrumentation Pipe in JMTR was established and organized by specialists from inside and outside JAERI on December 16. In order to investigate the cause of crack initiation at the pressure instrumentation pipe, the Working Group was organized in the Department of JMTR. Visual inspection, fractgraphy test, metallographic observation and hardness test for the pressure instrumentation pipe and its weldment were carried out in the JMTR Hot Laboratory. This report summarized above data obtained by investigation on the cause of the crack initiation.

Journal Articles

Indirect air cooling techniques for control rod drives in the high temperature engineering test reactor

Takeda, Takeshi; Tachibana, Yukio

Nuclear Engineering and Design, 223(1), p.25 - 40, 2003/07

 Times Cited Count:2 Percentile:19(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Report on the water leakage from instrumentation pipe in JMTR

JMTR Pressure Measurement Pipe Investigation Committee

JAERI-Review 2003-014, 117 Pages, 2003/03

JAERI-Review-2003-014.pdf:27.62MB

On December 10、2002, the leak was found at the pressure measurement pipe attached to the exit pipe of No.1 filing pump of the refining system of a primary cooling system at JMTR in Oarai Research establishment JAERI. Investigation Committee for Water Leakage from Instrumentation Pipe in JMTR was established and organized by specialists from inside and outside JAERI on December 16 and its meeting was held in public 3 times by 6th January, 2003. They investigated the cause and countermeasures of cracks, and also investigated enhancement of safety management. This is the report on the cause and countermeasures of cracks and enhancement of safety management.

JAEA Reports

Experimental study on sequential reactions in fusion reactor materials by D-T neutron irradiation

Hori, Junichi; Sato, Satoshi; Yamauchi, Michinori*; Ochiai, Kentaro; Nishitani, Takeo

JAERI-Research 2003-002, 50 Pages, 2003/03

JAERI-Research-2003-002.pdf:2.21MB

D-T neutron irradiation experiments have been performed with F82H and ODS ferritic steels and the effective cross sections for $$^{56}$$Co productions in those materials via the sequential reactions were measured. The effective cross sections for F82H and ODS ferritic steels were about 1.5 times larger than that for iron. The distributions of effective cross sections were measured for 6 materials (iron, copper, vanadium, titanium, tungsten and lead) and F82H. The sequential reaction rates in the region close to hydrogen compound became over 20 times larger than that in material itself. In the case of F82H, the increase ratio was about 50. It was indicated that the activity for the sequential reaction product $$^{56}$$Co will reach to 3-10 $$%$$ of that for primary neutron reaction product $$^{54}$$Mn aound the surface of a cooling pipe in a fusion reactor. The effective cross sections were estimated by using (n,xp), (p,n) reaction cross sections, proton emission spectra, proton stopping power in the material. The estimated values were compared with experimental results.

Journal Articles

Neutron streaming evaluation for the DREAM fusion power reactor

Seki, Yasushi; Mori, Seiji*; Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi

Journal of Nuclear Science and Technology, 37(Suppl.1), p.268 - 275, 2000/03

no abstracts in English

JAEA Reports

Development of pipe welding, cutting & inspection tools for the ITER blanket

Oka, Kiyoshi; *; *; *; Takahashi, Hiroyuki*; Tada, Eisuke

JAERI-Tech 99-048, 222 Pages, 1999/07

JAERI-Tech-99-048.pdf:24.01MB

no abstracts in English

Journal Articles

Blanket cooling pipe maintenance system for fusion experimental reactor

Oka, Kiyoshi; Kakudate, Satoshi; Nakahira, Masataka; *; Tada, Eisuke; *; Shibanuma, Kiyoshi; Haange, R.*; A.Tesini*

Fusion Technology 1996, 0, p.1649 - 1652, 1997/00

no abstracts in English

JAEA Reports

Development of remote bore tools for pipe welding/cutting by YAG laser

Oka, Kiyoshi; Nakahira, Masataka; Kakudate, Satoshi; Tada, Eisuke; Obara, Kenjiro; *; *

JAERI-Tech 96-035, 47 Pages, 1996/07

JAERI-Tech-96-035.pdf:3.17MB

no abstracts in English

Journal Articles

Verification study on alternative ECCS concepts for a PWR

; ; ; ;

Nucl.Eng.Des., 54(3), p.419 - 427, 1979/00

 Times Cited Count:1

no abstracts in English

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