Mitigation of steam generator tube rupture in a pressurized wate

Details Mitigation of steam generator tube rupture in a pressurized wate Mitigation of steam generator tube rupture in a pressurized wate

1992-06-24

1994-05-03

Wasil, Daniel D.

Induced nuclear reactions: processes, systems, and elements

Testing, sensing, measuring, or detecting a fission reactor...

Leak detection

376299, G21C 1518, G21C 17035

Patent

active

053094875

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.

REFERENCES:
patent: 3935738 (1976-02-01), Benham
patent: 4692297 (1987-09-01), Schlonski et al.
patent: 4753771 (1988-06-01), Conway et al.
Ronald Vijuk, et al., AP600 Offers a Simpler Way To Greater Safety, Operability and Maintainability, Nuclear Engineering International, Nov. 1988, pp. 22-28.

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