Published July 1979
| Version v1
Journal article
Thermal circuit and supercritical steam generator of the BGR-300 nuclear power plant
Description
Secondary coolant circuit and a steam generator for supercritical steam parameters of the BGR-300 reactor plant are described. The BGR-300 plant with a 300 MW(e) high-temperature gas-cooled fast reactor is developed as a pilot commercial plant. It is shown that the use of a supercritical pressure steam increases the thermal efficiency of the plant and descreases thermal releases to the environment, permits to use home-made commercial turbine plants of large unit power. The proposed supercritical pressure steam generator has considerable advantages from the viewpoint of heat transfer and hydrodynamical processes
Additional details
Additional titles
- Original title (Russian)
- Тепловая схема и парогенератор на закритические параметры пара реакторной установки BGR-300
Publishing Information
- Journal Title
- Teploehnergetika
- Journal Issue
- no.7
- Series
- Teploehnergetika.
- ISSN
- 0040-3636
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 14799940
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DIAGRAMS; FEEDWATER; GCFR TYPE REACTORS; HEAT EXCHANGERS; HELIUM; HELIUM COOLED REACTORS; HIGH PRESSURE; HIGH TEMPERATURE; OPTIMIZATION; SECONDARY COOLANT CIRCUITS; SPECIFICATIONS; STEAM GENERATORS; STEAM TURBINES; SUPERHEATERS; WATER VAPOR
- Descriptors DEC
- BOILERS; BREEDER REACTORS; COOLING SYSTEMS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; GAS COOLED REACTORS; GASES; HYDROGEN COMPOUNDS; INFORMATION; NONMETALS; OXYGEN COMPOUNDS; RARE GASES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; TURBINES; VAPOR GENERATORS; VAPORS; WATER
Optional Information
- Notes
- For English translation see the journal Thermal Engineering (UK).