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Steam system turbogenerator

The essential ingredients for producing heat in a thermal fission nuclear reactor are the fuel and a moderator. A heat transport system with its coolant is necessary to convey the heat from the reactor to boilers where steam is produced to drive the turbogenerator. The natural materials available for fuel and moderator are uranium ore and water natural uranium extracted from the ore comprises the fissionable isotope uranium-235 and water contains hydrogen which is a good moderator. (Table I)... [Pg.322]

One refrigeration system is electrically driven a second is operated by a condensing turbine. High pressure steam from a power house is pressure-reduced for use by the plant as it passes through one air compressor turbine, one refrigeration machine turbine, and the high pressure section of the turbogenerator. [Pg.95]

What is the total power required to run the plant at its rated capacity and how much power is getting generated through the steam turbogenerator How much is the surplus How much steam can be exported if cogeneration system is installed in the plant ... [Pg.42]

Figure XXI-6 shows the heat transport path from the core to the ultimate sink during normal operation and under emergency conditions. The normal heat removal system is based on a three-circuit design and includes a loopless (pool type) primary circuit in the reactor module, two equivalent loops of the intermediate sodium circuit, two loops of the steam-water circuit and a turbogenerator facility. During normal operation, heat released in the core, including residual heat release of the shutdown reactor is transferred to the steam-water circuit. Steam can be taken off from the third (steam-water) circuit for industrial applications and district heating. The steam-water circuit is designed to supply steam to the turbine generators of 500 or 800 MW power, taking the heat from three or five BMN-170 reactors. Figure XXI-6 shows the heat transport path from the core to the ultimate sink during normal operation and under emergency conditions. The normal heat removal system is based on a three-circuit design and includes a loopless (pool type) primary circuit in the reactor module, two equivalent loops of the intermediate sodium circuit, two loops of the steam-water circuit and a turbogenerator facility. During normal operation, heat released in the core, including residual heat release of the shutdown reactor is transferred to the steam-water circuit. Steam can be taken off from the third (steam-water) circuit for industrial applications and district heating. The steam-water circuit is designed to supply steam to the turbine generators of 500 or 800 MW power, taking the heat from three or five BMN-170 reactors.

See other pages where Steam system turbogenerator is mentioned: [Pg.143]    [Pg.367]    [Pg.465]    [Pg.435]    [Pg.143]    [Pg.367]    [Pg.521]    [Pg.367]    [Pg.110]    [Pg.2499]    [Pg.228]    [Pg.110]    [Pg.169]    [Pg.1178]    [Pg.2254]    [Pg.256]    [Pg.228]    [Pg.2503]    [Pg.45]    [Pg.728]    [Pg.294]    [Pg.470]    [Pg.417]    [Pg.168]    [Pg.61]   
See also in sourсe #XX -- [ Pg.465 , Pg.504 ]




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