Patent Number: 043303676
Section: claims

1. A protection apparatus for a nuclear power system which utilizes a quantitative relationship between a fuel cladding integrity index indicative of the proximity of the nuclear power system to a fuel cladding integrity design limit and select system parameters, said system having means for generating electrical parametric signals proportional to said select nuclear power system's parameters, said apparatus comprising: a. first means responsive to said electrical parametric signals for predicting the violation of said design limit by continuously approximating the projected value of said index and comparing the projected value of the index with said design limit;  b. second means responsive to said predicting means for initiating protective action for the prevention of the violation of said design limit; and  c. means for generating an operating limit on a select system parameter, said limit having a value which insures that said prediction and prevention means have adequate time to predict the violation of said design limit and to institute protective action for the prevention of said design limit violation;  d. wherein said means for generating an operating limit include third means responsive to said electrical parametric signals for determining a limiting value of said index which include an operating margin, said third means being more accurate than said first means, and fourth means for modifying in a real time one variable in said third means by a margin factor which depends on,  a. establishing a maximum allowable rate of approach to said nuclear power system design limit;  b. establishing said protection system's reaction time wherein said protection system's reaction time includes the time for the physical apparatus of the protection system to respond;  c. calculating from said equation, said select parameters, said maximum allowable rate of approach to said nuclear power system's design limit and said reaction time an operating limit having a value which allows sufficient margin for taking corrective action within said reaction time;  d. operating said nuclear power system on the basis of said operating limit;  e. predicting from said electrical signals indicative of said select parameter the violation of said design limit; and  f. commencing corrective action to prevent the violation of said design limit on the occurrence of said predicted violation.  a. multiplying a value equal to or greater than said maximum allowable rate of approach to said nuclear power system design limit by a value equal to or greater than said protection system's reaction time to obtain a modification value;  b. modifying said index by said modification value to obtain a modified index;  c. calculating said operating limit from said select system parameters and from said modified index by means of said equation which interrelates said index and said select parameters.  a. establishing a maximum allowable rate of approach to a minimum allowable value of DNBR;  b. establishing said protection system's reaction time;  c. calculating from said equation, from said parameters, from said maximum allowable rate of approach to said nuclear power system design limit and from said system reaction time an operating limit that allows sufficient margin for taking corrective action within said reaction time;  d. operating said nuclear power system on the basis of said operating limit;  e. predicting from said monitored nuclear power system's parameters the violation of said minimum allowable value of DNBR;  f. commencing corrective action on the occurrence of said predicted violation for the prevention of the violation of said minimum allowable value of DNBR. 2. The apparatus of claim 1 wherein said index is DNBR and said equation is an equation expressing DNBR. 3. The apparatus of claim 1 wherein said nuclear power system includes a nuclear reactor and wherein said select parameters include reactor coolant temperature, reactor coolant pressure, reactor coolant flow rate, reactor power, reactor core axial power distribution and reactor core integral radial power peaking factor. 4. An improved method for the operation of a protection system of a nuclear power system of the type which utilizes an equation which interrelates a fuel cladding integrity index indicative of the proximity of the nuclear power system to a nuclear power system fuel cladding design limit and selected parameters, said method including monitoring selected parameters and generating electrical signals indicative of said select parameters, the improved method comprising the steps of: 5. The improved method as recited in claim 4 wherein said step of calculating an operating limit having a value which allows sufficient margin for taking corrective action within said reaction time includes the steps of: 6. The improved method as recited in claim 4 wherein said index is DNBR and said equation is an equation expressing DNBR. 7. The improved method as recited in claim 4 wherein said nuclear power system includes a nuclear reactor and wherein said select parameters include reactor coolant temperature, reactor coolant pressure, reactor coolant flow rate, reactor power, reactor core axial power distribution and reactor core integral radial power peaking factor. 8. An improved method for the operation of a protection system of a nuclear power system of the type which utilizes an equation which interrelates DNBR and select nuclear power systems parameters, said method including monitoring select parameters and generating electrical signals indicative of said select parameters, the improved method comprising the steps of: