A new stage in the development of power engineering in Byelorussia
Description
The ways of development of power engineering in Byelorussia for the years of Soviet power is discussed. The main achievements with which the Byelorussian power engineering has came up to the 60-th anniversary stage in the development of the Byelorussian power system associated with building of atomic power stations with thermal and fast reactors in the nearest future is considered. Dissociating gas on nitrogen tetroxide basis is proposed for cooling of a fast nuclear reactor. Dissociating gas possessing low induced radioactivity can safely enter into the turbine next to the reactor. This gives the possibility to develop single-circuit power station and to provide the reduction in capital outlays on the project. High radiation resistance of the proposed coolant was found out, the availability of structural materials capable to operate in the medium of dissociating coolant and in the conditions of radiation needed for NPP development was set up
Additional details
Additional titles
- Original title (Russian)
- Новый этап развития энергетxки Белорусси
Publishing Information
- Journal Title
- Vestsi Akad. Navuk BSSR, Ser. Fiz.-Ehnerg. Navuk
- Journal Issue
- no.4
- Series
- Vestsi Akad. Navuk BSSR, Ser. Fiz.-Ehnerg. Navuk.
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 15014046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLANTS; DISSOCIATION; FAST REACTORS; NITROGEN OXIDES; NUCLEAR POWER PLANTS
- Descriptors DEC
- CHALCOGENIDES; EPITHERMAL REACTORS; NITROGEN COMPOUNDS; NUCLEAR FACILITIES; OXIDES; OXYGEN COMPOUNDS; POWER PLANTS; REACTORS; THERMAL POWER PLANTS