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temperature measurement for lamp-based heating deviceSumita, Takehiro; Sudo, Ayako; Takano, Masahide; Ikeda, Atsushi
Science and Technology of Advanced Materials; Methods (Internet), 2(1), p.50 - 54, 2022/02
Narukawa, Takafumi; Amaya, Masaki
Journal of Nuclear Science and Technology, 53(11), p.1758 - 1765, 2016/11
Times Cited Count：10 Percentile：67.99(Nuclear Science & Technology)Takada, Shoji; Sekita, Kenji; Nemoto, Takahiro; Honda, Yuki; Tochio, Daisuke; Inaba, Yoshitomo; Sato, Hiroyuki; Nakagawa, Shigeaki; Sawa, Kazuhiro
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05
To investigate the safety design criteria of heat utilization system for the HTGRs, it is necessary to evaluate the effect of fluctuation of thermal load on the reactor. The nuclear heat supply fluctuation test by non-nuclear heating was carried out to simulate the nuclear heat supply test which is carried out in the nuclear powered operation. The test data is used to verify the numerical code to calculate the temperature of core bottom structure to carry out the safety evaluation of abnormal events in the heat utilization system. In the test, the helium gas temperature was heated up to 120
C. A sufficiently high temperature disturbance was imposed on the reactor inlet temperature. It was found that the response of temperatures of metallic components such as side shielding blocks was faster than those of graphite blocks in the core bottom structure, which was significantly affected by the heat capacities of components, the level of imposed disturbance and heat transfer performance.
Takada, Shoji; Shimizu, Atsushi; Kondo, Makoto; Shimazaki, Yosuke; Shinohara, Masanori; Seki, Tomokazu; Tochio, Daisuke; Iigaki, Kazuhiko; Nakagawa, Shigeaki; Sawa, Kazuhiro
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05
In the loss of forced core cooling test using High Temperature engineering Test Reactor (HTTR), the forced cooling of reactor core is stopped without inserting control rods into the core and cooling by Vessel Cooling System (VCS) to demonstrate the inherent safety of HTGR be secured by natural phenomena to make it possible to design a severe accident free reactor. In the test, the local temperature was supposed to exceed the limit from the viewpoint of long-term use at the uncovered water cooling tube by thermal reflectors in the VCS, although the safety of reactor is kept. The local higher temperature position was specified although the temperature was sufficiently lower than the maximum allowable working temperature, and natural circulation of water had insufficient cooling effect on the temperature of water cooling tube below 1C. Then, a new safe and secured procedure for the loss of forced core cooling test was established, which will be carried out soon after the restart of HTTR.
Nagao, Yoshiharu; Itabashi, Yukio; Komori, Yoshihiro; Niimi, Motoji; Fujiki, Kazuo
KAERI/GP-195/2002, p.49 - 55, 2002/00
An improved analysis procedure has been introduced to evaluate irradiation field at each specimen in the irradiation capsule by using the MCNP code, which is able to model the complicated structure of the capsule directly. As the verification results, it was confirmed that the calculated fast and thermal neutron flux/fluence were agreed with measured ones within 
10% and 30%, respectively, for the irradiation tests in the JMTR. Concerning gamma dose/spectrum, it was confirmed that the calculated temperature was evaluated within -3
+14% using gamma heating obtained by MCNP calculations. The evaluations of neutron flux/fluence and specimens temperature with high accuracy are therefore possible in the irradiation test of the JMTR.
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of VHTRC-4 coreYamane, Tsuyoshi; Akino, Fujiyoshi;
PHYSOR 96: Int. Conf. on the Physics of Reactors, 2, p.E290 - E299, 1996/00
no abstracts in English
Nishimura, Akihiko; ; Oba, Hironori; Shibata, Takemasa
Journal of Nuclear Science and Technology, 30(3), p.270 - 273, 1993/03
Times Cited Count：13 Percentile：84.31(Nuclear Science & Technology)no abstracts in English
Hirayama, Toshio; Shirai, Hiroshi; Yagi, Masatoshi; Shimizu, Katsuhiro; Koide, Yoshihiko; Kikuchi, Mitsuru; Azumi, Masafumi
Nuclear Fusion, 32(1), p.89 - 106, 1992/00
Times Cited Count：7 Percentile：33.03(Physics, Fluids & Plasmas)no abstracts in English
; Akino, Fujiyoshi; Yamane, Tsuyoshi; ; Kitadate, Kenji; ; Takeuchi, Motoyoshi; Ono, Toshihiko; Kaneko, Yoshihiko
JAERI 1305, 138 Pages, 1987/08
no abstracts in English
; Akino, Fujiyoshi; ;
Journal of Nuclear Science and Technology, 24(6), p.431 - 441, 1987/06
Times Cited Count：2 Percentile：29.75(Nuclear Science & Technology)no abstracts in English
*; *; ; *; *
JAERI-M 86-084, 32 Pages, 1986/06
no abstracts in English
; ; ; Iwamoto, K.
JAERI-M 86-046, 17 Pages, 1986/03
no abstracts in English
; ; Iwamoto, K.
Transactions of the American Nuclear Society, 50, p.241 - 242, 1985/00
no abstracts in English
; ; ; ;
JAERI-M 9233, 53 Pages, 1980/12
no abstracts in English
Tone, Tatsuzo
Journal of Nuclear Science and Technology, 16(6), p.453 - 456, 1979/00
Times Cited Count：1no abstracts in English
; ; ;
Journal of Nuclear Science and Technology, 15(10), p.736 - 744, 1978/10
Times Cited Count：16no abstracts in English
; Yoneda, Yukio*
Bulletin of the Chemical Society of Japan, 41(4), p.824 - 827, 1968/00
Times Cited Count：0no abstracts in English
Chonan, Fuminori*; Abe, Yutaka*; Yuasa, Tomohisa*; Kaneko, Akiko*; Segawa, Tomoomi; Yamada, Yoshikazu
no journal, ,
In a reprocessing process of nuclear fuel cycle, an uranium-plutonium mixed oxide (MOX) raw powder is converted from a mixture solution of uranyl nitrate and plutonium nitrate by the microwave heating denitration method (MH method). The MH method is applied to remove water and nitric acid from a metallic nitrate solution, and a metallic oxide is obtained. In order to improve the efficiency of MH method, optimizing the equipment and conditions is needed to prevent flushing of a mixture solution during microwave heating. In our group, we have been studied that the influence of height of supporter which placed under the mixture solution in the vessel on its heating phenomena. Also we have been analyzed simulation of electromagnetic field during microwave heating in microwave oven. From those results, we considered the appropriate height of supporter in the oven. It was clarified that height of supporter was one of the important parameter for the efficiency of microwave heating.
