Experimental study of thermohydraulic processes and gas distribution in a model of the containment shell of the AST-500 reactor

Babykin, A. S.; Balunov, B. F.; Zhivitskaya, T. S.; Kuul, V. S.; Nosatov, V. N.; Fal'kov, A. A.

doi:10.1007/bf00760349

Cited by 7 publications

(1 citation statement)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…It is shown in [4] that a small velocity head of the steam corresponding to the velocity W 0 ″ ≥ 0.08-0.1 m/sec is sufficient for air, having a larger molecular mass and thus heavier, to be completely displaced upwards. For steam entering with this velocity, an isolated steam line 15-20% of the total length of the line is adequate to condense on the surface of the line.…”

Section: Effect Of the Position Of The Cooling Water Level In The Emementioning

confidence: 99%

Experimental studies of thermohydraulic processes for the passive heat-removal system at the Leningradskaya nuclear power plant

Kukhtevich¹,

Bezlepkin²,

Svetlov³

et al. 2010

At Energy

Self Cite

View full text Add to dashboard Cite

The results of experimental studies of a passive system for removing heat through steam generators which were performed on a large-scale (1/110) stand at the Scientific-Industrial Association for Research and Design of Power-Generation Equipment (NPO TsKTI, St. Petersburg) are presented. The experiments show that the system performs reliably and effectively as designed. The experimental data were used to verify the thermohydraulic codes KORSAR and SOKRAT, which are used to model the thermohydraulic processes in the system at the Leningradskaya nuclear power plant.The system for passively removing heat through steam generators is intended for removing residual heat from the core to the final absorber via the second loop during an unanticipated accident (complete loss of electric power to the nuclear power plant, complete loss of feed water, accident involving leaks in the first loop). The AES-2006 design developed by Atomenergoproekt St. Petersburg Research and Design Institute (SPbAEP) for the site of the second phase of the Leningradskaya nuclear power plant uses as the final absorber water which is stored in tanks used for emergency removal of heat and which boils off. The tanks are placed outside the protective shell at the 59 m marker and communicate with the atmosphere. A tubular, emergency cool-down, heat exchanger is placed at the bottom of the tanks; steam condenses and condensate cools down inside the heat exchanger during the downward motion of the second-loop coolant. The high heat-transfer coefficients, as compared with air-cooled heat-exchangers, and the high accumulation of energy absorbed by unit volume of water at atmospheric pressure as it is heated and then evaporates (2600 MJ/m 3 ), make it possible to create a compact system that passively removes heat at an acceptable rate until active measures can be taken to fill the emergency heat-removal tanks with water. The coolant to be cooled is transported from the steam generator to the heat-exchanger and back by means of natural circulation.The serviceability and effectiveness of the passive system designed by SPbAEP, were confirmed by large-scale experiments performed on an

show abstract

Section: Effect Of the Position Of The Cooling Water Level In The Emementioning

confidence: 99%