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C operation of the HTTRSakaba, Nariaki; Ohashi, Hirofumi; Takeda, Tetsuaki
Journal of Nuclear Materials, 353(1-2), p.42 - 51, 2006/07
Times Cited Count：11 Percentile：59.03(Materials Science, Multidisciplinary)The permeation of hydrogen isotopes through the Hastelloy XR high-temperature alloy adopted for the heat transfer pipes of the intermediate heat exchanger in the HTTR, is one of the concerns in the hydrogen production system, which will be connected to the HTTR in the near future. The hydrogen permeation between the primary and secondary coolant through the Hastelloy XR was evaluated using the actual hydrogen concentration observed during the initial 950C operation of the HTTR. The hydrogen permeability of the Hastelloy XR was estimated conservatively high as follows. The activation energy E
and pre-exponential factor F of the permeability of hydrogen were E = 65.8 kJ/mol and F = 7.8
10
m
(STP)/(m
sPa
), respectively, in the temperature range from 707K to 900K.
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.
Takeda, Takeshi; Tachibana, Yukio; Nakagawa, Shigeaki
JAERI-Tech 2002-091, 45 Pages, 2002/12
JAERI-Tech-2002-091.pdf:1.77MB
no abstracts in English
Inagaki, Yoshiyuki; ; ; ;
Nuclear Technology, 104, p.106 - 117, 1993/10
Times Cited Count：2 Percentile：29.46(Nuclear Science & Technology)no abstracts in English
Inagaki, Yoshiyuki; ; ; ; ;
JAERI-M 92-151, 49 Pages, 1992/10
no abstracts in English
Hada, Kazuhiko; Nishiguchi, Isoharu; ; Tsuji, Hirokazu
Nucl. Eng. Des., 132, p.1 - 11, 1991/00
Times Cited Count：25 Percentile：90.45(Nuclear Science & Technology)no abstracts in English
Tachibana, Yukio
no journal, ,
Japan Atomic Energy Agency (JAEA) has started the development of a domestic demonstration reactor based on the results of R&D activities conducted so far. In this presentation, an overview of the HTGR project, materials and operating conditions of HTTR high-temperature components will be presented, especially focusing on the development of intermediate heat exchangers and Hastelloy XR, and high-temperature structural design guidelines for HTGR Class 1 components will be introduced. In addition, future issues will be discussed.
