THE OVERVIEW OF THE LATEST DEVELOPMENTS OF PASSIVE SAFETY SYSTEMS FOR NPP WITH PRESSURIZED WATER REACTORS

Authors

  • Valerii Ivanovych Konshyn Національний технічний університет України «Київський політехнічний інститут імені Ігоря Сікорського», Ukraine
  • Roman Anatoliiovych Stremedlovskyi Національний технічний університет України «Київський політехнічний інститут імені Ігоря Сікорського», Ukraine

DOI:

https://doi.org/10.20535/1813-5420.1.2013.141461

Keywords:

core, reactor vessel, passive safety systems, containment vessel, the residual heat

Abstract

This article gives a brief overview of the current state of passive safety systems development for NPP with pressurized water reactors in the CIS as well as in the whole world. The passive systems of reactor cooling and heat removal are presented. The article presents and describes the elements of passive safety systems for NPP with WWER-1000/V-392. This article also gives an overview of the elements of passive safety systems for Advanced Passive (АР) reactors, ЕР-1000, APWR+ and IRIS. The article presents the formulated conclusions and tasks of the comprehensive feasibility study of the passive safety systems for the new generation of nuclear power plants. The study is based on international experience in design and operation of nuclear power plants.

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