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Title: Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems

The effects of steam generator tube ruptures in a pressurized water reactor are mitigated by reducing the pressure in the primary loop by diverting reactor coolant through the heat exchanger of a passive heat removal system immersed in the in containment refueling water storage tank in response to a high feed water level in the steam generator. Reactor coolant inventory is maintained by also in response to high steam generator level introducing coolant into the primary loop from core make-up tanks at the pressure in the reactor coolant system pressurizer. The high steam generator level is also used to isolate the start-up feed water system and the chemical and volume control system to prevent flooding into the steam header. 2 figures.
Authors:
; ;
Publication Date:
OSTI Identifier:
7201345
Report Number(s):
US 5309487; A
PPN: US 7-903683
DOE Contract Number:
AC03-90SF18495
Resource Type:
Patent
Resource Relation:
Patent File Date: 24 Jun 1992
Research Org:
Westinghouse Electric Corp
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR ACCIDENTS; STEAM GENERATORS; MITIGATION; RUPTURES; AUXILIARY WATER SYSTEMS; ENGINEERED SAFETY SYSTEMS; PRIMARY COOLANT CIRCUITS; ACCIDENTS; AUXILIARY SYSTEMS; BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS 220900* -- Nuclear Reactor Technology-- Reactor Safety; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled