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JAEA Reports

Evaluation of heat exchange performance for air-cooler in HTTR

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$$^{circ}$$C.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2002)

Department of HTTR Project

JAERI-Review 2003-043, 92 Pages, 2004/02

JAERI-Review-2003-043.pdf:5.76MB

The HTTR (High Temperature Engineering Test Reactor) with the thermal power of 30MW and the reactor outlet coolant temperature of 850/950$$^{circ}$$C is the first high temperature gas cooled reactor in Japan, which uses coated fuel particle, graphite for core components, and helium gas for primary coolant. In December 2001, the rated power of 30MW and the reactor outlet temperature of 850$$^{circ}$$C was attained. JAERI received the certificate of pre-operation test, that is, the commissioning license for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control and construction of components and facilities for the HTTR as well as R&D on HTGRs for FY2002.

JAEA Reports

Radiation monitoring data on the power-up test of HTTR; Results up to 20MW operation

Ashikagaya, Yoshinobu; Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji

JAERI-Tech 2001-092, 76 Pages, 2002/01

JAERI-Tech-2001-092.pdf:11.72MB

no abstracts in English

JAEA Reports

Development of a remote controlled fatigue testing apparatus at elevated temperature in controlled environment

Omi, Masao; Mimura, Hideaki; ; Fukaya, Kiyoshi; Yonekawa, Minoru; Goto, Ichiro; ; Saito, Junichi; Eto, Motokuni;

JAERI-Tech 96-005, 39 Pages, 1996/02

JAERI-Tech-96-005.pdf:2.28MB

no abstracts in English

JAEA Reports

Fracture toughness tests of 9 Cr type steels at elevated temperature; 2 nd. Report

*; ; ; *; *

PNC TN9410 91-132, 85 Pages, 1991/06

PNC-TN9410-91-132.pdf:1.47MB

A series of high temperature fracture toughness tests of 9Cr type steels was put in practice on a three-years scheme in 1988. In this experimental study, Mod.9Cr-1Mo steel, 9Cr-2Mo steel and 9Cr-1Mo-Nb-V steel are tested, and these fructure toughness are investigated on the basis of J integral. In a first year, high temperature fracture toughness test method was established using R-curve method and unloading compliance method, and J$$_{a}$$ values of Mod. 9Cr-1Mo steel were measured at RT, 400$$^{circ}$$C, 500$$^{circ}$$C, 550$$^{circ}$$C and 600$$^{circ}$$C. In a second year, fracture toughness tests of 9Cr-2Mo steel, 9Cr-1Mo-V-Nb steel and these aged materials were performed, and several factors which affected fracture toughness values of 9Cr type steels were clarified. In this report, the test results in a second year are summarized. In a last year, fracture toughness tests of weldment and thick plate of 9Cr type steel are going to be carried out. Furthermore, an effect of crack direction on J$$_{a}$$ value will be studied.

Oral presentation

Development of shear punch test technique for high-temperature strength evaluation of irradiated materials in the form of thin plate

Shizukawa, Yuta; Tanno, Takashi; Yano, Yasuhide

no journal, , 

no abstracts in English

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