Gaseous saturation of the primary circuit coolant in nuclear steam supply systems of water-moderated water-cooled power reactors

Journal Article · Thu Aug 01 00:00:00 EDT 1985 · Sov. At. Energy (Engl. Transl.); (United States)

DOI:https://doi.org/10.1007/BF01122207· OSTI ID:5903821

Kalaida, Y A; Esin, V I; Katkov, Y D; Khor'kov, M G; Lastochkin, A P; Perfil'ev, G E; Sysoev, V S

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.

• OSTI ID: 5903821
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Vol. 58:2; Other Information: Translated from Atomnaya Energiya, Vol. 58, No. 2, pp. 129-130, February, 1985
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
POWER REACTORS
REACTOR COOLING SYSTEMS
COOLANTS
COOLING
GAS SATURATION
PRIMARY COOLANT CIRCUITS
STEAM
STEAM GENERATORS
WATER
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTORS
SATURATION
VAPOR GENERATORS
220200* - Nuclear Reactor Technology- Components & Accessories