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

Optional Information

Notes
For English translation see the journal Thermal Engineering (UK).