Published August 1985
| Version v1
Journal article
Gaseous saturation of the primary circuit coolant in nuclear steam supply systems of water-moderated water-cooled power reactors
Description
An experimental study has been carried out on gas transfer from a gaseous volume compensator to a vessel, filled with water and periodically heated then cooled, having parameters typical of the primary circuit coolant in the NSSS of a water-moderated, water-cooled power reactor. It has been proved by experiment that the working gas concentration in a periodically heated then cooled primary circuit coolant can be higher than the gas concentration in the water in the compensators. During the operation of the NSSS of a water-moderated, water-cooled power reactor, circumstances exist in which the working gas concentration in the volume compensator in the primary circuit coolant system may be higher than in the water in the volume compensators
Additional details
Publishing Information
- Journal Title
- Sov. At. Energy (Engl. Transl.)
- Journal Volume
- 58
- Journal Issue
- 2
- Series
- Sov. At. Energy (Engl. Transl.).
- Journal Page Range
- 149-151
- ISSN
- 0038-531X
- CODEN
- SATEA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18082984
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COOLANTS; COOLING; GASES; POWER REACTORS; PRIMARY COOLANT CIRCUITS; REACTOR COOLING SYSTEMS; SATURATION; STEAM; STEAM GENERATORS; WATER
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; FLUIDS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; REACTOR COMPONENTS; REACTORS; SOLVENTS; VAPOR GENERATORS
Optional Information
- Notes
- Translated from Atomnaya Energiya, Vol. 58, No. 2, pp. 129-130, February, 1985.. Cover-to-cover translation of Atomnaya Ehnergiya (USSR).