Patent Number: 050154346
Section: claims

1. In a boiling water reactor having a reactor vessel, a core for containing a reaction within said reactor vessel, and a plurality of vertical in-core guide tubes extending from outside the reactor vessel into the core of said vessel at spaced apart locations, said vertical in-core guide tubes extending upwardly to the bottom of core to permit the insertion and removal of monitoring strings having local power range detectors for measuring the thermal neutron flux density interior of the core, the improvement comprising: a string having a plurality of local power range detectors, each monitor including a cathode; fissionable material on said cathode; an anode insulating material; and wiring connecting each said anode and cathode from a position on said string interior of said core to a position through said in-core guide tube exterior of said reactor vessel, each said local power range detector being placed in spaced apart relation along an end of said string whereby when said string is inserted to the end of said vertical guide tubes in said core, said local power range monitors will be in spaced vertical relation along said conduits in said core for measuring the thermal neutron flux;  said string having a corresponding plurality of gamma thermometers, each said gamma thermometer provided along the length of said string at a position immediately adjacent a local power range monitor, each said gamma thermometer for monitoring the temperature of said gamma thermometers with respect to a reference to determine the gamma flux of said reactor adjacent said local power range monitor whereby during conditions of steady state power operation readings of said gamma thermometers can be used for the calibration of said local power range monitors.  providing a monitoring string, said monitoring string having a plurality of local power range monitors including an anode, a cathode, fissionable material placed on said cathode and mineral insulated connecting each said anode and cathode in parallel to remote leads for connection to monitoring current reading instrumentation, each said local power range monitor being spaced in spaced apart relation along said string;  providing further in said string, gamma thermometers, each gamma thermometer including a mass for absorbing gamma rays and varying in temperature with respect to the flux of said absorbed gamma rays, said gamma thermometer including a reading thermocouple and a reference thermocouple;  each said gamma thermometer placed immediately adjacent a local power range monitors;  providing connection means for each said gamma thermometer to conventional paired leads for reading said thermocouples to determine gamma flux interior of said reactor;  operating said reactor at a steady power state;  taking an energy balance of said reactor to determine the reactor power output;  relating the power output at any portion of said reactor to a gamma thermometer reading;  taking the reading of a corresponding and immediately adjacent local power range monitor;  and calibrating the determined neutron flux from the reading of said local power range monitor to the reading of said gamma thermometer for the overall calibration of said local power range monitor. 2. The invention of claim 1 and including four local power range monitors and four or eight gamma thermometers on said string. 3. A process of calibrating local power range monitors in a boiling water reactor by a calibration detector inserted into a vertical in-core guide tube exterior of said vessel, said vertical in-core guide tube passing upward into the interior of said vessel core, said calibration process comprising the steps of;