Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems
Abstract
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.
- Inventors:
- Issue Date:
- Research Org.:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- OSTI Identifier:
- 7201345
- Patent Number(s):
- 5309487
- Application Number:
- PPN: US 7-903683
- Assignee:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- DOE Contract Number:
- AC03-90SF18495
- Resource Type:
- Patent
- Resource Relation:
- Patent File Date: 24 Jun 1992
- 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
Citation Formats
McDermott, D J, Schrader, K J, and Schulz, T L. Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems. United States: N. p., 1994.
Web.
McDermott, D J, Schrader, K J, & Schulz, T L. Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems. United States.
McDermott, D J, Schrader, K J, and Schulz, T L. Tue .
"Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems". United States.
@article{osti_7201345,
title = {Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems},
author = {McDermott, D J and Schrader, K J and Schulz, T L},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1994},
month = {5}
}
Search for the full text at the U.S. Patent and Trademark Office
Note: You will be redirected to the USPTO site, which may require a pop-up blocker to be deactivated to view the patent. If so, you will need to manually turn off your browser's pop-up blocker, typically found within the browser settings. (See DOE Patents FAQs for more information.)
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.