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Kuramochi, Masaya*; Yamamoto, Kazami; Kinsho, Michikazu
JAERI-Tech 2003-055, 148 Pages, 2003/07
JAERI-Tech-2003-055.pdf:24.48MB
The injection beam dump of the 3 GeV rapid cycling synchrotron (3 GeV-RCS) is to be installed to absorb the H
and H
beams that can not be changed into H
beam with a graphite foil. We estimate the maximum temperature and thermal stress of the injection beam dump. As a result, the temperature at the center region made of iron reached up to 370 K after several operation cycles (one cycle is three-week operation including one-week interval) under the 1kW-beam injection. Then, the temperature at the boundary between the iron region of the beam dump and the concrete wall of the tunnel was rather low temperature of about 320 K. And the maximum Mises stresses of 96 MPa and about 0.2 MPa were generated in the iron region and the concrete wall respectively. These values were much lower than the allowable temperature and stresses.
Takeda, Seietsu; ; ; Nakatsuka, Noboru; Nakano, Katsushi; ; Ishimaru, Tsunenori
JNC TN7410 2000-003, 65 Pages, 2000/11
Koshizuka, Seiichi*; *; Okano, Yasushi; *; Yamaguchi, Akira
JNC TY9400 2000-012, 91 Pages, 2000/03
JNC-TY9400-2000-012.pdf:2.82MB
no abstracts in English
; ; *
JNC TY7430 2000-001, 57 Pages, 2000/03
JNC-TY7430-2000-001.pdf:2.17MB
no abstracts in English
Kita, Haruyuki*; Nakata, Masao*; *
PNC TJ7176 98-003, 68 Pages, 1998/03
no abstracts in English
Futakawa, Masatoshi; Takada, Shoji; *; Iyoku, Tatsuo
Nucl. Eng. Des., 166, p.47 - 54, 1996/00
Times Cited Count：4 Percentile：39.42(Nuclear Science & Technology)no abstracts in English
*
PNC TN9410 90-096, 162 Pages, 1990/06
Thermal transient strength tests in using the Thermal Transient Strength Test Facility for Structures (TTS) have been carried out to develop the design method for fast breeder reactor components under thermal loadings. The design and the fabrication of the Welded Vessel Model which is to be tested at TTS are described in this report. In this model, the noteworthy typical shape and stress distribution as seen in the structural design of Large Fast Breeder Reactor (LFBR) and the modified SUS316 which is a hopeful material for LFBR are incorporated. The Welded vessel Model is a cocoon-like model which has 25mm thickness, 2210mm hight and 850mm inner diameter, and it has seven test portions of interest, namely inlet/outlet nozzle, upper/skirt Y-janctions, vessel ring, inner shell ring and inner shell support flange. In design of this model, thermal transient conditions were established by performing Hydraulic-thermal analyses, and then, heat transfer analyses and thermal stress analyses were performed. Test portions of interest were evaluated using the special design guide for TTS tests. Materials and welding method adopted are basically the ones applicable to LFBR's reactor structures.
*
PNC TN9410 90-054, 125 Pages, 1990/01
A preliminary analysis was performed on the sodium thermal fatigue tests which are planned to be conducted with the "Sodium Thermal Fatigue Test Apparatus", which was recently constructed in the material development section. This test machine was constructed for the purpose of aquisition of data needed for sofistication of the evaluation method of creep-fatigue and crack propagation of welded joints. This preliminary analysis is concerned with thermal analysis and stress analysis on test specimens which are planed to be used in the machine. Effects of following parameters on temperature/stress distribution of test specimens under various conditions were analysed. Thcse parameters are considered to play significant roles in the analysis of the results of upcoming experiments. (1)Heat transfer coefficient (2)Thermal shock temperature (3)Speed of submerging specimen (4)Comparison of behavior of base metal and welded joint (5)Comparison of mechanical loading and thermal loading
Qin, T. Y.*; Zhang, H.*; Zhou, L.*; Ao, N.*; Xu, P. G.; Su, Y. H.; Wu, S. C.*; Shobu, Takahisa
no journal, ,
