Patent Number: 048636738
Section: claims

1. In a hydraulically actuated control rod drive of the type including: a reactor vessel having a pressurized interior;  a core in said reactor vessel containing fissionable materials;  a control rod for movement into and out of said core for the control of fission in said fissionable material of said nuclear reactor, said control rod moveable against ambient pressure interior of said reactor;  a hydraulic fluid pressure source;  means for moving said control rod into and out of said core in said nuclear reactor, said means including a hydraulic actuator for urging said control rod into insertion within said core of said reactor, said hydraulic actuator communicated to said hydraulic fluid pressure source through a hydraulic circuit;  a check valve in said hydraulic circuit between said hydraulic actuator and said hydraulic fluid pressure source for preventing reverse flow of said hydraulic circuit responsive to the ejection of said control rod by ambient pressure within said reactor vessel, the improvement to said hydraulic circuit comprising a hydraulic conduit between said check valve and said hydraulic fluid pressure source;  an isolation valve for isolating said conduit;  a positive displacement piston and cylinder having a beginning piston stroke and an ending position stroke with a known positive displacement of fluid between said beginning and ending stroke position corresponding to insignificant ejection of said control rod from said reactor vessel;  means for timing movement of said piston between said respective stroke positions for determining the rate of displacement of hydraulic fluid through said check valve; and  means for connecting said piston through said isolation valve to said check valve whereby fluid passing through said check valve causes movement of said piston to indicate closure and integrity of said check valve without appreciable control rod ejection from said reactor.  means for actuating said first microswitch upon admitting fluid to said piston and cylinder;  means for actuating said second microswitch upon end of stroke of said piston within said piston and cylinder.  providing a connected test conduit between said check valve and said fluid pressure source for enabling said check valve to seat upon flow through said conduit;  providing a constant displacement hydraulic piston and cylinder, said piston having a stroke excursion within said cylinder for providing positive and known displacement, said displacement of said piston and cylinder corresponding to minimal ejection of said control rod from said core of said reactor;  connecting said piston to said test conduit;  permitting flow through said test conduit to said piston;  timing the stroke of said piston in said piston cylinder whereby the integrity of said check valve is indicated as a function of the stroke of said piston with respect to time with short stroke indicating lack of check valve integrity and long stroke indicating check valve seating and sealing. 2. The invention of claim 1 and including a first and second microswitch; 3. The invention of claim 2 and wherein a timer is started by said first microswitch and stopped by said second microswitch. 4. The invention of claim 1 and including a quick disconnect between said positive displacement piston and said isolation valve for isolating said conduit. 5. A process for testing a check valve in a control rod drive in a nuclear reactor wherein a reactor vessel contains a core in a pressurized fluid environment and a control rod movable by a hydraulic piston by force through and from a hydraulic circuit into and out of the pressurized environment of said reactor vessel against the pressure of said pressurized environment, said hydraulic circuit including a fluid pressure source for insertion of said control rod and a conduit from said fluid pressure source to said hydraulic piston for inserting of said control rod and a check valve in said conduit between said pressure source and actuator for preventing reactor pressure ejection of said control rod from said reactor, the process for testing of the operation and integrity of said check valve comprising the steps of: