Презентация на тему Analysis of possible application of high-temperature nuclear reactors to contemporary large output steam power plants on ships

to contemporary large output steam power plants on ships
Nizhny

Novgorod State Technical University n.a. R. E. Alekseev

Made by:
student of
M16-YAE
D.N.Smirnov

Reactor (PWR)
parameters of live steam in steam cycle: 300°C

and 4 MPa

High Temperature Reactor (HTR)
parameters of live steam in steam cycle: 535°C and 10 MPa

of Xe-135 poisoning during start-ups and power reduction

overheat

net electric efficiency ηnetto, average mechanical efficiency of the

turbines, ηT, the relative steam flux mx/m0 and the relative turbine inlet pressure in function of changes in the power plant load Nx/NG for the “twin” cycle

net electric efficiency ηnetto, average mechanical efficiency of HP

and LP part of the turbine, ηT, as well as the relative steam flux mx/m0, all in function of change in the power plant load Nx/NG for the cycle with interstage overheat

used at nuclear power plants at the present time.
The

analysis of the efficiency characteristics that single-case steam turbines operating under a simple thermodynamic cycle, doubled or multiplied in ship power plant, are able to ensure a higher energy conversion efficiency of power plant at partial loads. The idea of application of high-temperature, graphite-moderated, helium-cooled nuclear reactors eliminates operational disadvantages of contemporary ship nuclear power plants by increasing their parameters over those of contemporary conventional steam power plants.
Application of HTR reactors improves hence profitability of ship nuclear power plants compared to today used PWR reactors, increases their safety and lowers hazards to the environment.