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International Journal of Energy for a Clean Environment
Главный редактор: Ashwani K. Gupta (open in a new tab)
Исполнительный редактор – Южная Америка: Marcelo J.S. de Lemos (open in a new tab)
Управляющий редактор: Andrey Kuzmin (open in a new tab)

Выходит 8 номеров в год

ISSN Печать: 2150-3621

ISSN Онлайн: 2150-363X

SJR: 0.597 SNIP: 1.456 CiteScore™:: 3.7 H-Index: 18

Indexed in

THERMOSIPHON−BASED PASSIVE HEAT REMOVAL SYSTEM FOR SIMULTANEOUS COOLDOWN OF REACTOR AND PRESSURIZER

Том 13, Выпуск 1-4, 2012, pp. 153-167
DOI: 10.1615/InterJEnerCleanEnv.2013006206
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Краткое описание

The article discusses a proposal to introduce an autonomous passive heat removal system (PHRS) to increase the safety of nuclear power plants with the water-moderated water-cooled power reactor (WWER−1000) nuclear reactor. The residual heat is removed via heat exchangers composed from two-phase thermosiphons. The system operability can be maintained even under loss of all external power sources. The advantage of the system is its direct connection with the primary coolant circuit that provides the system compatibility with all types of light-water reactors. The system has three safety barriers to prevent activity release into the environment for any expected combinations of failures. The results of the analytical modeling carried out show that the suggested passive system provides conditions for timely injection of boric acid from hydro-accumulators (HAs) and thus sufficient subcriticality during the entire emergency process simultaneously with maintaining subcooling of the primary coolant. The results of analytical modeling of emergency cooldown of the reactor installation during a complete, long-term blackout event are presented. It is proved that the proposed PHRS provides efficient heat sink and primary depressurization. That provides conditions for actuation of the emergency core cooling system (ECCS) HAs and maintains adequate subcriticality during the transient along with maintaining subcooling conditions of the primary coolant in the reactor core.

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