Emergency core cooling systems

被引:0
|
作者
Gonyaeva, Sofya S. [1 ]
Kozhemyakin, Vyacheslav V. [1 ]
Kozhemyakin, Vladimir O. [1 ]
Morozov, Nikita A. [1 ]
Nikolaeva, Sofya A. [2 ]
Apollova, Anastasia V. [1 ]
机构
[1] State Marine Tech Univ St Petersburg, Dept Ship Nucl & Hydrogen Energet, Lotsmanskaya 3, St Petersburg 190121, Russia
[2] State Marine Tech Univ St Petersburg, Grp 2163, Lotsmanskaya 3, St Petersburg 190121, Russia
来源
关键词
passive heat removal system; steam-water jet apparatus; reactor plant; cooling down; bypassing;
D O I
10.37220/MIT.2024.63.1.012
中图分类号
U6 [水路运输]; P75 [海洋工程];
学科分类号
0814 ; 081505 ; 0824 ; 082401 ;
摘要
Paper is devoted to the development of a system for passive heat removal from the reactor, capable of providing normal and emergency cooldown of the reactor, as well as ensuring the operation of the plant at low reactor power without the participation of a steam turbine plant. It is proposed to ensure the circulation of the coolant in this system using steam-water jet apparatus with a subsonic steam nozzle, similar to those previously developed for the type << Beta >> integral reactor. Systems with such jet apparatuses are prone to parameter pulsation due to breakdowns and restarts of steam-water jet apparatuses. Taking this in consideration a system configuration was proposed that makes it possible to regulate the power supplied by the steam generator and removed by the outboard heat exchanger, thereby excluding pulsations in the system and disruptions of the steam-water jet apparatus. Bypassing the steam generator prevents too wet steam from being released into the system.
引用
收藏
页码:105 / 109
页数:5
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