Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site

Bakhmet’ev, A. M.; Bol’shukhin, M. A.; Vakhrushev, V.V.; Khizbullin, A. M.; Makarov, O. V.; Bezlepkin, V. V.; Semashko, S. E.; Ivkov, I. M.

doi:10.1007/s10512-009-9150-1

Cited by 23 publications

(3 citation statements)

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“…Nuclear safety has attracted increasing global attention after the Fukushima accident. The passive containment cooling system (PCCS) has been used in third-generation nuclear power plants (NPPs) [1][2][3].…”

Section: Introductionmentioning

confidence: 99%

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Time-Average Heat Transfer Coefficient for Steam-Air Condensation during the Dropping of Containment Pressure

Li¹,

Hui

Ke³

et al. 2022

Energies

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The passive containment cooling system (PCCS) has been applied in the new generation nuclear power plant. Previous studies mainly focused on steady-state heat transfer, but the actual heat transfer of PCCS is the transient process. Thus, investigating the transient heat transfer during the containment pressure dropping is necessary. The present study proposes a time-average condensation heat transfer coefficient (time-average condensation HTC) to characterize the intensity of transient condensation heat transfer. The time-average condensation HTC is defined as the heat absorbed per unit heat transfer area and per unit wall subcooling in a unit time. Experiments were performed to research the effect of initial gas-mixture pressure and air mass fraction on transient HTC. The result showed that the more significant gas-mixture pressure and lower air mass fraction could promote the transient-state heat transfer, especially the low air mass fraction. Based on the experimental result, a detailed empirical correlation for the time-average heat transfer coefficient is developed with an error of ±20%. Another simplified empirical correlation that only includes air mass fraction is also proposed to predict the transient heat transfer roughly. Besides, research on self-sustaining stability is also conducted to evaluate the stable operation characteristic of PCCS. The system can respond quickly and then run to a new steady state after interference during the long-term operation of PCCS. The phenomenon above implies that PCCS has good self-sustaining stability.

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Section: Introductionmentioning

confidence: 99%

“…AP1000 [4], VVER1200 [1] and HPR1000 [3] as new generation nuclear power plants have been most widely applied. Although both AP1000 and HPR1000 adopt passive safety technology, different methods are used in these two types of nuclear power plants.…”

Section: Introductionmentioning

confidence: 99%

Time-Average Heat Transfer Coefficient for Steam-Air Condensation during the Dropping of Containment Pressure

Li¹,

Hui

Ke³

et al. 2022

Energies

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“…One is termed 'external condenser' if steam condenses on the outer surface of the condenser tubes placed near the top of the containment. This is used in the KERENA (formerly SWR1000) (Stosic et al, 2008), AHWR (Sinha and Kakodkar, 2006;Kakodkar, 2014), HPR1000 (Xing et al, 2016), iPower (Lee et al, 2017), and WWER-1200 (Bakhmet'ev et al, 2009;Bezlepkin et al, 2014) reactors. Another is termed 'internal condenser' if steam condenses inside the condenser tubes.…”

Section: Introductionmentioning

confidence: 99%

Effect of condenser tube inclination on the flow dynamics and instabilities in a passive containment cooling system (PCCS) for nuclear safety

Haag

Selvam

Leyer

2020

Nuclear Engineering and Design

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Stability of the water-chemistry regime in the loop of a passive safety system of nuclear power reactors

et al. 2010

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The organization of the water-chemistry regime in the loop of a passive safety system, whose purpose is emergency removal of heat from the core of a nuclear power reactor, is examined. It is shown that a selfregulated water-chemistry regime in which gaseous products of radiolysis can be dissolved in water coolant and recirculated into the irradiation zone, which will intensify liquid-phase radiation-chemical reactions of hydrogen with oxygen and organic release of gases from the liquid phase into the vapor-gas phase of the coolant, can arise in the loop of a passive safety system. This will result in the establishment in the loop of dynamic equilibrium between the release and dissolution of gases and will enable prolonged functioning of the safety system without intervention from the outside. The physicochemical and technical criteria for the appearance of a self-regulated water-chemistry regime for closed loops with natural circulation of the two-phase coolant are formulated and substantiated.A passive cool-down system is a promising solution for increasing the safety of the first loop of a nuclear power facility [1]. It must remain serviceable during a prolonged period of time not only without the intervention of plant workers but also in the absence of electricity. Independence of operation from energy input and protection from failures of active components can be attained by implementing the principle of internal self-protection -the use of natural processes, specifically, natural circulation of the coolant and self-regulated water-chemistry and gas regimes.The present article examines a passive system for emergency cool-down of a nuclear power facility with two loops (Fig. 1): loop for cooling down the reactor facility and an ammonia cooling loop. A characteristic of the system studied here is the lack of blow-offs intended for removing uncondensed gases.The purpose of the cool-down loop is to remove heat directly from the reactor facility. It consists of sections of heat exchange with the reactor loop and condensation of the vapor formed. The water coolant moves from the bottom of the heatexchange section by means of an ascending flow, where it is heated to the temperature of saturation, evaporation, and superheating of the steam. The superheated steam flows along the discharge steam lines into the ammonia heat-exchanger, which releases heat to the cooling loop with ammonia, after which it returns to the entrance of the heat-exchange section.As it moves through the heat-exchange section, the coolant is heated by neutron and gamma radiation, which forms radiolytic gases. In the case of a closed loop without blow-offs, the uncondensed gas -hydrogen and oxygen -accumulates in the coolant, which can disrupt the functioning of the facility, specifically, lower the operating efficiency of the condenser and, as a result, disrupt coolant circulation.General Approach to Modeling the Water-Chemistry and Gas Regime in the Loop of a Passive System. The present article proposes an approach to modeling the water-chemistr...

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Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site

Cited by 23 publications

References 0 publications

Time-Average Heat Transfer Coefficient for Steam-Air Condensation during the Dropping of Containment Pressure

Time-Average Heat Transfer Coefficient for Steam-Air Condensation during the Dropping of Containment Pressure

Effect of condenser tube inclination on the flow dynamics and instabilities in a passive containment cooling system (PCCS) for nuclear safety

Stability of the water-chemistry regime in the loop of a passive safety system of nuclear power reactors

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