A THERMAL CYCLE FOR NUCLEAR POWER PLANT WITH GAS COOLED REACTOR (in Czech)
The effects of the cooling gas temperature at the reactor inlet, reheating of vapor from the low pressure turbine. and preheating the feed water on the efficiency of one or two stage vapor cycles generated in a steam generator and on the circulating gas blower input were evaluated. The influence ef the parameter changes, the costs of primary cycle, and the breeding of nuclear fuel were not considered. The results showed that the suggested thermal cycle with two pressure stages (70 to 160 atm. and 15 to 26 atm.) with preheating of the feed water and reheating ef vapor affected the gas temperature of 175 to 250 deg C at the inlet and of 400 to 500 deg C at the outlet of the reactor. The thermal efficiency of the power plant was 27.6 to 32.6%. (tr-auth)
- Research Organization:
- V.I. Lenin's Plant, Pilsen
- NSA Number:
- NSA-12-007508
- OSTI ID:
- 4335526
- Journal Information:
- Jaderna Energie, Journal Name: Jaderna Energie Vol. Vol: 4, No. 1
- Country of Publication:
- Country unknown/Code not available
- Language:
- Czech
Similar Records
INTERIM REFERENCE DESIGN GAS-COOLED, HEAVY-WATER-MODERATED PRESSURE-TUBE REACTOR PROTOTYPE (GCPTR)
THE ANALYSIS OF THERMAL ECONOMY OF ATOMIC POWER PLANTS, ARRANGED WITH A GAS COOLANT