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High temperature test reactor HTTR

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

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]

Saito, S. et al., Design of high temperature engineering test reactor (HTTR), JAERI, 1332,1994. [Pg.159]

The HTTR is an experimental helium-cooled 30 MW(t) reactor. The HTTR is not designed for electrical power production, but its high temperature process heat capability makes it worthy of inclusion here. Construction started in March 1991 [47] and first criticality is expected in 1998 [48]. The prismatic graphite core of the HTTR is contained in a steel pressure vessel 13.3 m in height and 5.5 m in diameter. The reactor outlet coolant temperature is 850°C under normal rated operation and 950°C under high temperature test operation. The HTTR has a primary helium coolant loop with an intermediate helium-helium heat exchanger and a pressurized water cooler in parallel. The reactor is thus capable of providing... [Pg.473]

Figure 3 High-temperature engineering test reactor (HTTR)... Figure 3 High-temperature engineering test reactor (HTTR)...
I am sure that you will all join me in offering our best wishes of success to this new Agency. I am also very pleased to note the collaboration between this third NEA information exchange meeting and the second High-Temperature Engineering Test Reactor (HTTR) workshop by the IAEA. These two meetings have been wisely combined and there will be a special session on the third day devoted mainly to HTTR related applications. [Pg.11]

S. Ueta, J. Sumita, K. Emori, M. Takahashi, K. Sawa, Fuel and fission gas behavior during rise-to-power test of the High Temperature Engineering Test Reactor (HTTR) , J. Nucl. Sci. Technol., 40[9], 679, (2003). [Pg.176]


See other pages where High temperature test reactor HTTR is mentioned: [Pg.503]    [Pg.524]    [Pg.503]    [Pg.31]    [Pg.333]    [Pg.451]    [Pg.480]    [Pg.503]    [Pg.524]    [Pg.503]    [Pg.31]    [Pg.333]    [Pg.451]    [Pg.480]    [Pg.96]    [Pg.9]    [Pg.11]    [Pg.55]    [Pg.478]    [Pg.525]    [Pg.452]    [Pg.142]    [Pg.506]    [Pg.48]    [Pg.49]    [Pg.485]    [Pg.3]    [Pg.46]    [Pg.59]    [Pg.81]    [Pg.308]    [Pg.7]    [Pg.15]    [Pg.16]    [Pg.131]    [Pg.132]    [Pg.138]   
See also in sourсe #XX -- [ Pg.452 ]

See also in sourсe #XX -- [ Pg.452 ]

See also in sourсe #XX -- [ Pg.452 ]




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