Patent Number: 047708433
Section: claims

1. A method of controlling the stability of the fuel assemblies in a boiling water reactor core comprising the steps of: (a) monitoring on an on-line basis the values of selected reactor parameters incuding, flow, inlet subcooling, control rod position, and pressure;  (b) determining on a real time basis from the selected reactor parameters, the power generated in, and the axial power distribution for, each fuel assembly;  (c) selecting fuel assemblies with axial power peaking occurring below a predetermined location as determined from said axial power distributions, and with a power level above a selected value;  (d) calculating on-line in a digital computer a stability index only for said selected fuel assemblies; and  (e) generating a human readable representation of the stability indexes in real time for the selected fuel assemblies.  iteratively calculating the stability index for said least stable fuel assembly incremental changes in a selected one of the axial power distribution and flow parameters until said stability index for the least stable fuel assembly is reduced at least to said preselected stability limit; and  operating reactor controls to implement the cumulative change in the selected one parameter to bring the stability index for the least stable fuel assembly down to at least said preselected limit.  (a) measuring on an on-line basis reactor parameters including, flow, temperature, control rod position and pressure,  (b) operating a digital computer to generate from said measured reactor parameters, nodal distributions of selected reactor parameters with at least one node per fuel assembly in the radial plane and a plurality of spaced nodes in the axial direction; to calculate from said selected nodal distributions, a stability index for selected fuel assemblies, taking into account core physical parameters which are a measure of power level, axial power distribution, flow, enthalpy, void drift, detailed fuel rod dynamics, nuclear reactivity feedback and, where appropriate, flow cross-coupling in the radial and axial directions; to determine the least stable selected fuel assembly from said calculated stability indexes; and to interatively recalculate the stability index for an unstable least stable selected fuel assembly using assumed incremental changes in a selected one of the rod position and flow parameters until said recalculated stability index for the least stable fuel assembly represents a stable condition; and  (c) generating output representations of the calculated stability indexes and of the cumulative change in said selected parameter required to make the least stable fuel assembly stable; and  (d) adjusting the reactor controls to change said selected one parameter by said cumulative change to bring said least stable fuel assembly to a stable condition.  means for measuring on-line, selected reactor parameters including: flow, temperature, control rod position and pressure;  a digital computer programmed: to identify in real time from the selected reactor parameters those fuel assemblies having inlet power peaking and above average power levels; to calculate only for the identified fuel assemblies a stability index taking into account hydrodynamic and nuclear feedback effects; and to generate output signals representative of said stability indexes; and  means for generating human readable representations of said identified fuel assemblies and their stability indexes from said output signals.  a reactor core having a plurality of fuel assemblies;  control rods for adjusting the reactivity of said fuel assemblies in the reactor core;  flow control means for controlling the flow of reactor coolant through the fuel assemblies of the reactor core;  means for measuring selected reactor parameters including: flow, control rod position, temperature and pressure;  digital computer means programmed: to generate nodal distributions of selected reactor parameters, with at least one node per fuel assembly in the radial plane and a plurality of spaced nodes in the axial direction; to select, using said nodal distributions, fuel assemblies having their peak axial power at a location below a selected location and having a power level above a preselected level to calculate from said nodal distributions a stability index for said selected fuel assemblies taking into account physical parameters which are a measure of power level, axial power distribution, flow, enthalpy, void drift, detailed fuel rod dynamics, nuclear reactivity feedback, and where appropriate, flow cross-coupling in the radial and axial directions; to determine the least stable selected fuel assembly from the calculated stability indexes; to iteratively recalculate the stability index for an unstable least stable selected fuel assembly using assumed incremental changes in a selected one of the rod position and flow parameters until said recalculated stability index for the least stable fuel assembly represents a stable condition; and to generate a control signal representative of the cumulative assumed changes in the selected one parameter; and  control means to which said control signal is selectively applied to change the selected one of rod position or flow by the assumed cumulative amount.  means for measuring on an on-line basis selected reactor parameters including flow, temperature, control rod position and pressure;  a digital computer programmed to: (a) determine the radial and axial power distribution on a per fuel bundle basis using said selected parameters, (b) determine the peaking location for the axial power distribution for each fuel bundle and the average power level for the fuel bundles, (c) determine the stability margins only for those fuel bundles for which axial power peaking occurs below the average peaking location and for which the power level is above said average power level, and (d) iteratively repeat step (c) using incremental adjustments in a designated one of the flow and rod position parameters to determine a change in the designated parameter required to bring the stability margins for the selected fuel bundles within designated limits; and  means for implementing said change in the designated parameter. 2. The method of claim 1 wherein said step of selecting fuel assemblies comprises determining the average axial location of axial power peaking and the average power for all of said fuel assemblies, and selecting those fuel assemblies with axial power peaking occurring below said average axial location and with power above said average power. 3. The method of claim 1 including: determining the least stable fuel assembly from said stability indexes calculated for said selected fuel assemblies, comparing the stability index of the least stable fuel assemblies to a preselected stability limit, and where said stability index for said least stable fuel assembly exceeds the preselected limit: 4. The method of claim 3 wherein said step of operating reactor controls to implement the cumulative change in the selected one parameter includes generating a control signal representative of the change required in the selected parameter and applying the control signal to an automatic controller to automatically effect the change in the selected one parameter. 5. The method of claim 3 wherein said monitoring step includes generating a real time power-flow map from said selected parameters and wherein said selected one parameter is flow, and said iterative calculations are carried out using incremental increases in flow and corresponding incremental increases in power determined from said power-flow map. 6. The method of claim 1 wherein said calculation of said stability indexes by said digital computer comprise nodal calculations with radially distributed nodes for each fuel assembly and a plurality of axially spaced nodes, and which incorporate nodal values of physical parameters which are a measure of nuclear feedback as well as the hydrodynamics of the flow channels. 7. A method of controlling the stability of the fuel assemblies in a boiling water reactor core comprising the steps of: 8. The method of claim 7 including operating said digital computer to select said fuel assemblies for which a stability index is calculated by determining for each fuel assembly, the power level, and from the axial power distributions, the location of the axial power peaking, and selecting those fuel assemblies with a power level above a preselected level and with axial power peaking occurring below a preselected axial location. 9. The method of claim 8 including operating said digital computer: to determine the average power level in said fuel assemblies and the average location of axial power peaking; and to select those fuel assemblies in which the power level is above said average power level, and in which axial power peaking occurs below said average location of axial power peaking. 10. A system for controlling instability in the fuel assembly of a boiling water reactor comprising: 11. The system of claim 10 wherein said digital computer is further programmed: to identify from the stability indexes the least stable fuel assembly; to iteratively recalculate the stability index for an unstable least stable fuel assembly using assumed incremental changes in a selected one of control rod position and flow parameters until the recalculated stability index for the least stable fuel assembly represents a stable condition; and to generate a control signal representative of the assumed cumulative change in the selected one parameter, said system including control means to which said control signal can be applied for changing the selected one parameter by the amount of the assumed cumulative change. 12. A boiling water reactor comprising: 13. Apparatus for controlling the stability of the fuel bundles in a boiling water reactor comprising: