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Iyoku, Tatsuo; Sakaba, Nariaki; Nakagawa, Shigeaki; Tachibana, Yukio; Kasahara, Seiji; Kawasaki, Kozo
Nuclear Production of Hydrogen, p.167 - 176, 2006/00
no abstracts in English
Tochio, Daisuke; Nakagawa, Shigeaki
JAERI-Tech 2005-041, 109 Pages, 2005/08
JAERI-Tech-2005-041.pdf:4.48MB
In High Temperature Engineering Test Reactor (HTTR) of 30MW, the generated heat at reactor core is finally dissipated at the air-cooler by way of the heat exchangers of the primary pressurized water cooler and the intermediate heat exchanger. To remove generated heat at reactor core and to hold reactor inlet coolant temperature to specified temperature, heat exchangers in main cooling system of HTTR should have designed heat exchange performance. In this report, heat exchange performance for ACL in main cooling system is evaluated with previous operation data, and evaluated values are compared with designed value. Moreover, heat exchange performance at full power operation is estimated for the air temperature. As the result, ACL has heat exchange performance removing generated heat at reactor core under the designe ACL inlet air temperature of 33
C.
Tochio, Daisuke; Nakagawa, Shigeaki
JAERI-Tech 2005-040, 39 Pages, 2005/07
JAERI-Tech-2005-040.pdf:1.88MB
In High Temperature Engineering Test Reactor (HTTR) of 30 MW, the generated heat at reactor core is finally dissipated at the air-cooler by way of the heat exchangers of the primary pressurized water cooler and the intermediate heat exchanger. Heat exchangers in main cooling system of HTTR should satisfy two conditions, achievement of reactor coolant outlet temperature 850 C/950 C and removal of reactor generated heat 30 MW. That is, heat exchange performance should be ensured as that in heat exchanger designing. In this report, heat exchange performance for Intermediate heat exchanger (IHX) in main cooling system is evaluated with rise-to-power-up test and in-service operation data. Moreover, the applicability of IHX thermal-hydraulic design method is discussed with comparison of evaluated data with designed value.
Sakaba, Nariaki; Tachibana, Yukio; Onuki, Kaoru; Komori, Yoshihiro; Ogawa, Masuro
Nuclear Engineering International, 50(612), p.20 - 22, 2005/07
The HTTR (High Temperature Engineering Test Reactor) at Japan Atomic Energy Research Institute's Oarai Research Establishment attained its maximum reactor-outlet coolant temperature of 950C in April 2004 and ready to connect nuclear heat for industrial applications. The hydrogen production system by thermochemical water-splitting Iodine Sulphur cycle is also developing and succeeded to produce 30 normal L/h hydrogen in a closed cycle in June 2004.
C in HTTRKawasaki, Kozo; Iyoku, Tatsuo; Tachibana, Yukio; Nakazawa, Toshio; Goto, Minoru
Proceedings of 13th International Conference on Nuclear Engineering (ICONE-13) (CD-ROM), 8 Pages, 2005/05
High Temperature Engineering Test Reactor (HTTR) achieved a coolant temperature of 950C at reactor outlet with its rated thermal power of 30MW on April 19, 2004. Achievement of the reactor outlet coolant temperature of 950C makes it possible to extend use of high-temperature gas-cooled reactors beyond the field of electric power generation. Not only highly effective power generation with a high-temperature gas turbine system but also hydrogen production from water without emission of carbon dioxide will be possible utilizing the high temperature heat. This report describes the results of the high-temperature test operation of the HTTR.
Ashikagaya, Yoshinobu; Kawasaki, Tomokatsu; Yoshino, Toshiaki; Ishida, Keiichi
JAERI-Tech 2005-010, 81 Pages, 2005/03
JAERI-Tech-2005-010.pdf:16.65MB
no abstracts in English
C in HTTRIyoku, Tatsuo; Nakagawa, Shigeaki; Takamatsu, Kuniyoshi
UTNL-R-0446, p.14_1 - 14_9, 2005/03
no abstracts in English
C in HTTRFujikawa, Seigo; Hayashi, Hideyuki; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo; Nakagawa, Shigeaki; Sakaba, Nariaki
Journal of Nuclear Science and Technology, 41(12), p.1245 - 1254, 2004/12
Times Cited Count：89 Percentile：97.72(Nuclear Science & Technology)A High Temperature Gas-cooled Reactor (HTGR) is particularly attractive due to its capability of producing high-temperature helium gas and to its inherent safety characteristics. The High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan, achieved its rated thermal power of 30MW and reactor-outlet coolant temperature of 950C on 19 April 2004. During the high-temperature test operation which is the final phase of the rise-to-power tests, reactor characteristics and reactor performance were confirmed, and reactor operations were monitored to demonstrate the safety and stability of operation. The reactor-outlet coolant temperature of 950C makes it possible to extend high-temperature gas-cooled reactor use beyond the field of electric power. Also, highly effective power generation with a high-temperature gas turbine becomes possible, as does hydrogen production from water. The achievement of 950C will be a major contribution to the actualization of producing hydrogen from water using the high-temperature gas-cooled reactors. This report describes the results of the high-temperature test operation of the HTTR.
CKawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo
Nihon Genshiryoku Gakkai-Shi, 46(8), P. 510, 2004/08
no abstracts in English
C for the first time in the worldKawasaki, Kozo; Iyoku, Tatsuo; Nakazawa, Toshio; Hayashi, Hideyuki; Fujikawa, Seigo
Nihon Genshiryoku Gakkai-Shi, 46(5), P. 301, 2004/05
no abstracts in English
