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:
-
- Export, PA
- Penn Hills, PA
- Murrysville Boro, PA
- Issue Date:
- Research Org.:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 869282
- Patent Number(s):
- 5309487
- Assignee:
- Westinghouse Electric Corp. (Pittsburgh, PA)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G - PHYSICS G21 - NUCLEAR PHYSICS G21D - NUCLEAR POWER PLANT
- DOE Contract Number:
- AC03-90SF18495
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- mitigation; steam; generator; tube; rupture; pressurized; water; reactor; passive; safety; systems; effects; ruptures; mitigated; reducing; pressure; primary; loop; diverting; coolant; heat; exchanger; removal; immersed; containment; refueling; storage; tank; response; feed; level; passive heat; passive safety; water level; water reactor; pressurized water; water storage; storage tank; reactor coolant; steam generator; heat exchange; heat exchanger; heat removal; refueling water; safety systems; generator tube; feed water; tube rupture; primary loop; /376/
Citation Formats
McDermott, Daniel J, Schrader, Kenneth J, and Schulz, Terry L. Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems. United States: N. p., 1994.
Web.
McDermott, Daniel J, Schrader, Kenneth J, & Schulz, Terry L. Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems. United States.
McDermott, Daniel J, Schrader, Kenneth J, and Schulz, Terry L. Sat .
"Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems". United States. https://www.osti.gov/servlets/purl/869282.
@article{osti_869282,
title = {Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems},
author = {McDermott, Daniel J and Schrader, Kenneth J and Schulz, Terry 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 = {Sat Jan 01 00:00:00 EST 1994},
month = {Sat Jan 01 00:00:00 EST 1994}
}
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