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High-temperature test reactor

High Temperature Test Reactor, HTTR (Japan)... [Pg.452]

The helium-cooled, high temperature test reactor of the Arbeitsgemeinschaft Versuchsreaktor (AVR) (thermal power 45 MJ/s, electrical power 15 MW) was operated for approximately 127,000 hours and approximately 45,000 hours at a helium temperature of 950 °C. Besides its function as an integral test reactor for spherical fuel elements, valuable experiences were gained for the typical helium systems and components. [Pg.237]

Fig. 4.17. Japanese High-Temperature Test Reactor fuel assembly with fuel rod. Fig. 4.17. Japanese High-Temperature Test Reactor fuel assembly with fuel rod.
The core outlet temperature is set to 900°C, which is below what has been, or will be demonstrated, by the fuels in AVR (Arbeitsgemeinschaft Versuchs Reaktor), HTR-10, HTTR (High Temperature Test Reactor), etc. No safety hazard of water or steam ingress into the primary system exists, since all water and steam circulation is remotely located in the third loop. The nitrogen heater is essentially pressure balanced with a slightly higher secondary pressure to ensure that no fission products enter the secondary system in case of leaking tubes. [Pg.537]

HTR-10 High-temperature test reactor 10 MW in Tsinghua University s INET... [Pg.88]


See other pages where High-temperature test reactor is mentioned: [Pg.503]    [Pg.524]    [Pg.503]    [Pg.96]    [Pg.9]    [Pg.14]    [Pg.31]    [Pg.11]    [Pg.69]    [Pg.333]    [Pg.451]    [Pg.42]    [Pg.55]    [Pg.408]    [Pg.525]    [Pg.480]   
See also in sourсe #XX -- [ Pg.142 , Pg.143 , Pg.144 , Pg.145 , Pg.146 , Pg.147 , Pg.148 , Pg.149 , Pg.150 , Pg.151 , Pg.152 , Pg.153 , Pg.154 ]




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