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Kawamura, Sho; Kikuchi, Masanobu; Hosoya, Toshiaki
JAEA-Technology 2021-041, 103 Pages, 2023/02
JAEA-Technology-2021-041.pdf:8.7MB
In response to new regulatory standard for research and test reactor which is enforced December 2013, JRR-3 got license in November 2018 by formulate new design basis ground motion. After that we evaluated for insertion property of control rod using that new design basis ground motion, and that evaluation results were accepted as approval of the design and construction method by Nuclear Regulation Authority. Now, we re-evaluated to insertion property of control rod about neutron absorber and follower fuel element by time history response analysis method. In this report, it shows that new results have sufficiency of margin compared with the past results that are accepted as approval of the design and construction method.
Nishihara, Tetsuo; Inagaki, Yoshiyuki
Nuclear Technology, 153(1), p.100 - 106, 2006/01
Times Cited Count：9 Percentile：53.38(Nuclear Science & Technology)Japan Atomic Energy Research Institute (JAERI) has performed the research and development of hydrogen production using the high temperature engineering test reactor (HTTR). One of the key issues for the HTTR hydrogen production system is the development of control technology for stable operation. A thermal load absorber concept using a steam generator installed downstream of a reformer is proposed to mitigate a variation of helium temperature. Thermal hydraulic analyses for the start up operation and the suspension of feed gas supply to the reformer are carried out. These results show that a large variation of the reformer outlet helium temperature takes place due to a change of the feed gas flow rate. However the steam generator can mitigate the variation of helium temperature. It is clarified that the HTTR can continue normal operation independently of the feed gas flow rate.
Ono, Tomio*; Subekti, M.*; Kudo, Kazuhiko*; Takamatsu, Kuniyoshi; Nakagawa, Shigeaki; Nabeshima, Kunihiko
Nihon Genshiryoku Gakkai Wabun Rombunshi, 4(2), p.115 - 126, 2005/06
Control-rod withdrawal tests simulating reactivity insertion are carried out in the HTTR to verify the inherent safety features of HTGRs. This paper describes pre-test analysis method using artificial neural networks to predict the changes of reactor power and reactivity. The network model applied in this study is based on recurrent neural networks. The inputs of the network are the changes of the central control rods position and other significant core parameters, and the outputs are the changes of reactor power and reactivity. Furthermore, Time Synchronizing Signal(TSS) is added to input to improve the modeling of time series data. The actual tests data, which were previously carried out in the HTTR, were used for learning the model of the plant dynamics. After the learning, the network can predict the changes of reactor power and reactivity in the following tests.
Tachibana, Yukio; Sawahata, Hiroaki; Iyoku, Tatsuo; Nakazawa, Toshio
Nuclear Engineering and Design, 233(1-3), p.89 - 101, 2004/10
Times Cited Count：10 Percentile：55.72(Nuclear Science & Technology)no abstracts in English
Takada, Eiji*; Fujimoto, Nozomu; Matsuda, Atsuko*; Nakagawa, Shigeaki
JAERI-Tech 2003-040, 23 Pages, 2003/03
JAERI-Tech-2003-040.pdf:1.28MB
In the High Temperature Engineering Test Reactor (HTTR), since the primary circuit is very high at the high temperature test operation, the special alloy Alloy800H is used as the metallic material for cladding tubes and spines of the control rods to endure the temperature of 950 degrees centigrade. The control rod is supposed to be exchanged for the excess use of its temperature limit 900 degrees centigrade according to the strength data of Alloy800H. The scram shutdown by loss of off-site electric power at the high temperature test operation is assumed as an event of the temperature of the control rods to exceed 900 degrees centigrade. In this report, the temperature of the control rods is analyzed by using the measurement data of the rise-to-power test. The result of this analysis it is confirmed that the control rod temperature does not exceed its limitation value even after the most temperature raises event of the loss of off-site electric power at the high temperature test operation.
Nishihara, Tetsuo; Inagaki, Yoshiyuki
Proceedings of GLOBAL2003 Atoms for Prosperity; Updating Eisenhower's Global Vision for Nuclear Energy (CD-ROM), p.320 - 324, 2003/00
HTGR hydrogen production system has potential possibility to provide hydrogen without CO
emission. Key technology for developing this system is to establish the control technology for preventing propagation of thermal turbulence from the hydrogen production system to the HTGR. Japan Atomic Energy Research Institute (JAERI) has planed a demonstration test of hydrogen production using an HTGR named high temperature engineering test reactor (HTTR) to develop the control technology. Thermal load absorber concept using the steam generator located downstream of the chemical reactor is proposed to mitigate the variation of outlet helium temperature of the chemical reactor. This concept leads to the stable controllability and enables to operate the HTGR and the hydrogen production plant independently. Plant simulation analyses are carried out to verify the performance of this concept.
Takeda, Hayato*; Onuma, Kenji*; Tamada, Masao; Kasai, Noboru; Katakai, Akio; Hasegawa, Shin; Seko, Noriaki; Kawabata, Yukiya*; Sugo, Takanobu
JAERI-Tech 2001-062, 66 Pages, 2001/10
Real sea experiment for the recovery of significant metals such as uranium and vanadium has been carried out at the offing of Mutsu establishment to evaluate the adsorption performance of adsorbent synthesized by radiation-induced graft-polymerization. After elution of uranium and vanadium from the adsorbent, their metals were adsorbed onto the conventional chelate resin. This chelate resin in a plastic column was further put in a cylindrical stainless transport container. The container was transported to the facility for separation and purification by a truck for the exclusive loading. The maximum concentration is 60 Bq/g when the uranium is adsorbed on the chelate resin. Transportation of recovered metals can be treated as general substance since these amount and concentration are out of legal control. However, the recovered metals were transported in conformity to L type transportation as a voluntary regulation. The strength analysis of the container was equal to the safety level of IP-2 type which is higher transportation grade than L type .
Okumura, Susumu; Kurashima, Satoshi; Ishimoto, Takayuki*; Yokota, Wataru; Arakawa, Kazuo; Fukuda, Mitsuhiro; Nakamura, Yoshiteru; Ishibori, Ikuo; Nara, Takayuki; Agematsu, Takashi; et al.
Proceedings of 13th Symposium on Accelerator Science and Technology, p.283 - 285, 2001/00
no abstracts in English
Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro; Haga, Katsuhiro
JAERI-Tech 97-050, 125 Pages, 1997/10
no abstracts in English
Tachibana, Yukio; Shiozawa, Shusaku; *; *; *
Nucl. Eng. Des., 172(1-2), p.93 - 102, 1997/00
Times Cited Count：8 Percentile：56.36(Nuclear Science & Technology)no abstracts in English
Takeda, Takeshi; Kunitomi, Kazuhiko; Okubo, Minoru
Nihon Genshiryoku Gakkai-Shi, 38(4), p.307 - 314, 1996/00
no abstracts in English
Arika, Mitsuhiro*
JAERI-M 94-045, 132 Pages, 1994/03
no abstracts in English
Araya, Fumimasa; Iwamura, Takamichi; Okubo, Tsutomu; ; Murao, Yoshio
Nihon Genshiryoku Gakkai-Shi, 34(8), p.776 - 786, 1992/08
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Nakagawa, Shigeaki; Sawa, Kazuhiro; Ohashi, Kazutaka*
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.299 - 304, 1991/00
no abstracts in English
Nakamura, Yukiharu; Ozeki, Takahisa
JAERI 1317, 310 Pages, 1989/03
no abstracts in English
Matsuura, Shojiro*
JAERI-M 84-138, 246 Pages, 1984/08
no abstracts in English
JAERI-M 84-077, 49 Pages, 1984/04
no abstracts in English
Matsuura, Shojiro
JAERI-M 83-129, 246 Pages, 1983/09
no abstracts in English
JAERI-M 82-114, 197 Pages, 1982/09
no abstracts in English
; ; ;
JAERI-M 9911, 32 Pages, 1982/02
no abstracts in English
