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Shibata, Taiju; Kikuchi, Takayuki; Miyamoto, Satoshi*; Ogura, Kazutomo*
Nuclear Engineering and Design, 223(2), p.133 - 143, 2003/08
Times Cited Count：1 Percentile：10.46(Nuclear Science & Technology)The High Temperature Engineering Test Reactor (HTTR) can provide very large spaces at high temperatures for irradiation tests. The I-I type irradiation equipment was developed as the first irradiation rig. It will be served for an in-pile creep test on a stainless steel with large standard size specimens. It uses the ambient high temperature of the core for the irradiation temperature control. The target irradiation temperatures are 550 and 600
C with the target temperature deviation of 
3C. In this study, the irradiation temperature changes at transient conditions were analyzed by an FEM code and the temperature controllability of the equipment was examined by a mockup test. The controllability was evaluated with the measured temperature transient data at the core graphite components in the Rise-to-Power tests of the HTTR. The result indicates that the temperature control method of the equipment is effective to keep the irradiation temperature stable in the irradiation test.
Takeda, Takeshi; Tachibana, Yukio
Nuclear Engineering and Design, 223(1), p.25 - 40, 2003/07
Times Cited Count：3 Percentile：24.96(Nuclear Science & Technology)no abstracts in English
Kaji, Yoshiyuki; Matsui, Yoshinori; Kita, Satoshi; Ide, Hiroshi; Tsukada, Takashi; Tsuji, Hirokazu
Nuclear Engineering and Design, 217(3), p.283 - 288, 2002/09
Times Cited Count：4 Percentile：28.08(Nuclear Science & Technology)In the Japan Atomic Energy Research Institute (JAERI), in-pile strain measurement techniques have been developed using the Japan Materials Testing Reactor (JMTR). In order to evaluate the performance of fiber optic grating sensors under irradiation environment, heat-up and performance tests at elevated temperatures before irradiation and in-pile tests were performed in JMTR. It was determined that it is possible to measure strain under irradiation environment below 1
1023n/m
(E
1MeV) by a fiber optic grating sensor, because in-pile temperature characteristics were in good agreement with out-of-pile test results.
Takeda, Takeshi; Furusawa, Takayuki; Shinozaki, Masayuki*; Miyamoto, Satoshi*
Nuclear Engineering and Design, 217(1-2), p.153 - 166, 2002/08
Times Cited Count：3 Percentile：22.28(Nuclear Science & Technology)no abstracts in English
Haga, Katsuhiro; Terada, Atsuhiko*; Kaminaga, Masanori; Hino, Ryutaro
Nuclear Engineering and Design, 210(1-3), p.157 - 168, 2001/12
Times Cited Count：4 Percentile：32.52(Nuclear Science & Technology)The mercury target is used in the spallation neutron source driven by a high intensity proton accelerator. In this study the effectiveness of the cross-flow type mercury target structure was evaluated experimentally and analytically. Prior to the experiment, the mercury flow field and the temperature distribution in the target container were analyzed assuming the proton beam energy and power of 1.5GeV and 5MW. Then the average water flow velocity field in the target mock-up model, which was fabricated from plexiglass for a water experiment, was measured at room temperature using the PIV technique. Water flow analyses were also conducted. The experimental results showed that the cross-flow could be realized in most of the proton beam path area and the analytical result of the water flow velocity field showed good correspondence to the experimental result in the case of the Reynolds number of more than 4.83E5 at the model inlet. With these results, the effectiveness of the cross-flow type mercury target structure and the present analysis code system was demonstrated.
Sawa, Kazuhiro; Suzuki, Shuichi*; Shiozawa, Shusaku
Nuclear Engineering and Design, 208(3), p.305 - 313, 2001/09
Times Cited Count：42 Percentile：91.84(Nuclear Science & Technology)no abstracts in English
Shibata, Katsuyuki; Kato, Daisuke*; Li, Y.*
Nuclear Engineering and Design, 208(1), p.1 - 13, 2001/08
Times Cited Count：21 Percentile：79.02(Nuclear Science & Technology)no abstracts in English
Kaji, Yoshiyuki; Gu, W.*; Ishihara, Masahiro; Arai, Taketoshi; Nakamura, Hitoshi*
Nuclear Engineering and Design, 206(1), p.1 - 12, 2001/05
Times Cited Count：10 Percentile：57.59(Nuclear Science & Technology)no abstracts in English
