Creation of Post-Accident Sampling System of Water-Water Energy Reactor

Abstract

The article describes the stages of creation of the Russian PASS system (Post-Accident Sampling System). The IAEA gives special attention to availability of PASS after analysing the consequences of the accident at Fukushima-Daiichi nuclear power plant. This system is necessary to examine the state of water-water power reactors in the mode of ceasing the normal operation. As an object for analysis, the coolant of the primary reactor loop and of environment auxiliary reactor systems was selected. As a part of the work on the system, solutions on the hydraulic scheme, solutions on automation of the sampling process, as well as issues of ensuring the safety of sampling for the personnel and the reactor as a whole were worked out.