Patent Number: 054901847
Section: description

DESCRIPTION OF THE PREFERRED EMBODIMENT FIG. 1 illustrates a nuclear electric power generating plant 1 in which a nuclear steam supply system (NSSS) 3 supplies steam for driving a turbine-generator 5 to produce electric power. The NSSS 3 has a pressurized water reactor (PWR) 7 which includes a reactor core 9 housed within a reactor vessel 11. Fission reactions within the core 9 generate heat which is absorbed by a reactor coolant, light water, which is passed through the core. The heated coolant is circulated through a hot leg 13 to a steam generator 15. Reactor coolant is returned to the reactor 3 from the steam generator by a reactor coolant pump (RCP) 17 through a cold leg 19. Typically, a PWR has at least 2 and often 3 or 4 steam generators 15 each supplied with heated coolant through a hot leg 13 forming with a cold leg and an RCP 17 a primary loop, and each supplying steam to the turbine-generator 5. For clarity, only one loop has been shown. Coolant returned to the reactor flows downward through an annular downcormer 18 and then upward through the core 9 in the direction indicated by the arrows in FIG. 1. The reactivity of the core 9, and therefore the power output of the reactor, is controlled on a short term basis by control rods 20 which may be selectively inserted into the core 9. Long term reactivity is regulated through control of the concentration of a neutron moderator such as boron dissolved in the coolant. Regulation of the boron concentration affects reactivity uniformly throughout the core as the coolant circulates through the entire core. On the other hand, the control rods 20 affect local reactivity and therefore, result in an asymmetry of axial and radial power distribution within the core 9. Conditions within the core 9 are monitored by several different sensor systems. These include the excore detector system 21 which measures neutron flux escaping from the reactor vessel. The excore system 21 includes source range detectors (not shown) used when the reactor is shut-down, intermediate range detectors (also not shown) used during start-up and shut-down, and power range detectors used when the reactor is above about 5% power. The power range excore detectors comprise top and bottom equal length un-compensated ion chambers 21.sub.t and 21.sub.b stacked on top of each other to form a power range excore detector channel. There are four power range detector channels (only 2 shown in FIG. 1) symmetrically located, radially and axially, just outside the reactor vessel 11. Older PWR's are equipped with a moveable incore detector system 23. This system includes moveable detectors 25 which are inserted into the reactor core through tubes 27. These moveable detectors 25 are used by the system 23 to map the axial and radial power distribution in the core 9. Newer PWR's are provided with strings of fixed incore detectors 29 in place of, or in some instances in addition, to the moveable incore detector system 23. The moveable incore detector system 23 is used only periodically, such as once a month. On the other hand, the fixed incore detectors permit continual mapping of the axial and radial power distribution within the core such as, for instance, every few minutes. Instrumentation relevant to the present invention also includes resistance temperature detectors (RTDs) 31 which measure the core inlet temperature. RTDs 31 are provided for each of the loops of a multi-loop system. An array of core exit thermocouples (TCs) 33 are distributed across the top of the reactor core to measure core exit temperatures. These core exit temperatures can be utilized by a system such as that described in U.S. Pat. No. 4,774,050 which is hereby incorporated by reference as another means for determining core axial and radial power distribution. The currents measured by the detectors 21.sub.t and 21.sub.b of each of the channels of the power range excore detectors system 21, the inlet temperature measured by the RTDs 31 and the output of the moveable detector system 23 and the core exit temperatures measured by the thermocouples 33 are all provided to the power monitoring system 35 which provides an absolute measurement of core power in a manner to be discussed below. The core power signal generated by the system 35 can be used in a known manner in the reactor control and protection systems. Reactor coolant heated as it passes through the reactor core 9 is delivered through the hot leg 13 to the steam generator 15 where it converts feed water delivered through the feedwater system 37 into steam which is delivered through the steam line 39 to the turbine generator 5. The flow of feedwater to the steam generator 15 is measured by a venturi 41. As mentioned above, the power which can be generated by the PWR 7 for licensing purposes is determined by a calorimetric measurement calculated from parameters including feedwater flow measured by the venturi 41. It is fouling of this venturi 41 over time which creates the error in the thermal power calculations referred to above. In accordance with the present invention, only a thermal power measurement taken at a base time when the venturi 41 is not fouled, or at some other time when the thermal power is known to be accurate, is used to calibrate the power range excore detector power measurement. As indicated above, the reactor power determined from the Power Range excore detectors 21.sub.t and 21.sub.b is subject to power indication deviations caused by relative changes in the core axial and radial power distribution, in addition to the changes caused by variations in the absolute core power output. The indicated power from the Power Range channels is also subject to errors caused by changes in the density of the water in the vessel downcomer region 18 and fuel that occur when the vessel inlet temperature changes. In order to utilize the Power Range channels for power indication in an absolute sense, the factors which cause non-power level changes in the excore detector currents must be understood and compensated for in the relationship between excore detector signal level and core power level. The Power Range excore detector current for the top detector 21.sub.t in a Power Range channel (I.sub.t) for a core of height H may be expressed: ##EQU1## where: A.sub.t =a parameter proportional to the top detector sensitivity and detector/core geometry; .SIGMA..sub.R =the effective macroscopic removal fast neutron cross section of the material between the core and the detector; PA1 d.sub.t =the effective distance between the top excore detector and the assemblies contributing to the signal measured by the detector; PA1 w.sub.t (z)=an axial weighting factor for the top detector which describes the relative contribution of neutrons produced at core axial location z, in the vicinity of the excore detector, to the total signal measured by the detector; PA1 P.sub.r =the core relative power level, in terms of fraction of full power, and; PA1 P.sub.wa (z)=the radially weighted core relative power distribution at core elevation z. Equal to the sum of products of relative assembly powers and the corresponding radially varying weighting factors. PA1 T.sub.i.sup.R =the value of T.sub.i present when the reference conditions are measured. A w.sub.t (z) function needs to be developed for each PWR application of this methodology. The axial power weighting factor may even be unique to each detector in every excore detector channel. This function is developed utilizing shielding type neutron transport codes as known in the art, and once established should not change unless the physical characteristics of the detector, or the detector/core geometry, are changed. An example of this type of function is shown in FIG. 2, where the curves 45 and 47 represent the top and bottom detector weighting factors respectively. The radial relative assembly power weighting factors used to develop the value of P.sub.wa (z) are not a function of axial core position. They are developed for each type of plant (e.g., 2 loop, 3 loop, 4 loop), using methods similar to the axial weighting factor determination methods. An example of the radial weighting factors used for a 4 loop plant is provided to FIG. 3. Equation 1 describes what excore detector current would be observed at a combination of reactor axial and radial power distribution conditions, and core power level, with explicit consideration given to changes in the environment between the fast neutron sources in the core and the detector. The ability to determine the influences of these factors on the excore detector currents allows the excore detectors to be used in an absolute fashion to determine reactor power level. The complexity of determining the value of A.sub.t and .SIGMA..sub.R makes Equation 1 of little practical benefit. However, the form and fashion of Equation 1 does allow for the fairly straightforward determination of changes in the excore detector currents from a reference set of conditions. The reference conditions may be expressed in an equation of the form: ##EQU2## where the superscript R denotes the reference condition value of the parameters defined for Equation 1. The determination of changes in the excore detector currents due to core power distribution and detector/core environmental condition changes from a reference condition allows the actor power level to be determined accurately from the excore detector currents. For ease of notation, define the integral portions of Equations 1 and 2 to be the following: ##EQU3## where the superscript R denotes the reference value. The ratio of the measured top detector current to the detector current measured at the reference condition may be expressed: ##EQU4## The value A.sub.t should be the same as the reference value of A.sub.t, unless the detector/core geometry changes or the detector sensitivity changes in the time interval between the reference and current measurements. Therefore, the A coefficients will cancel in Equation 5, and the actual core power level may be expressed: ##EQU5## Equation 6 may be solved directly utilizing measured conditions for all the parameters except the .SIGMA..sub.R 's and d.sub.t. The values of the reference and current .SIGMA..sub.R values will have a temperature dependence not expressed in Equation 6. In order to account for the temperature dependence of the .SIGMA..sub.R values, a simple temperature dependent expression for .SIGMA..sub.R.sup.R, relative to the reference .SIGMA..sub.R, may be developed. The value of .SIGMA..sub.R which exists following a deviation in the core downcomer and fuel region water temperature from the reference condition, assuming a linear variation in .SIGMA..sub.R with temperature over the range of applicability, may be expressed: ##EQU6## where: T.sub.i =the vessel inlet temperature measured by the RTD 33 in the vessel inlet located nearest the encore detector channel, and; Substituting this expression for .SIGMA..sub.R into Equation 6 yields: ##EQU7## Equation 8 contains the temperature correction necessary to compensate the excore detector indicated power for downcomer and fuel region temperature variations, but can not be solved until the partial differential term and effective distance term in the exponential portion of the equation are known. It is not necessary to determine the partial differential and effective distance terms in Equation 8 separately or analytically in order to properly utilize the equation to determine an accurate compensated excore detector power. Determining the product of these terms will suffice. Solving Equation 8 for the product in the exponent yields: ##EQU8## The value of K.sub.t can be determined from measurements at two different temperatures and power levels during actor start-up testing, and should remain essentially constant from one cycle to the next. A typical value in a four loop plant for K.sub.t is 0.012/.degree.F. Utilizing the definition of K.sub.t in Equation 9, Equation 8 becomes: ##EQU9## An expression of the form of Equation 10 may be developed for both the top and bottom detector in each encore detector channel. The subscript "t" is replaced with the subscript "b" in Equation 10 for the bottom detector in the channel. Separate axial power weighting factors are needed for the bottom section detectors. The average of all the excore detector compensated relative power values is the most accurate indication of core power, relative to the reference condition accuracy, available from the excore detectors. FIG. 4 is a flow chart for a program 49 for determining the constant K used to make adjustments for changes in temperature. A value for K is calculated for each detector. As shown at 51, the first step is to determine the radial relative assembly power weighting factors for each detector channel i for each x, y radial core location j as shown for instance in FIG. 3. The axial weighting factors for each measured core axial interval, z, for radially weighted relative assembly power for each detector j and each channel i is then determined at 53 using for instance the weighting factors illustrated in FIG. 2. Next the measured reactor three-dimensional power distribution, thermal power level, excore detector signals, and vessel inlet temperatures at the two different power settings P.sub.1 and P.sub.2 are determined at 55 and 57. Then, at 59, Q.sub.wa is calculated for each channel i at the power levels P.sub.1 and P.sub.2. Finally, the constant K is calculated for each detector j at 61. FIG. 5 is a flow chart for a program 63 which can be used by a computer in the core monitoring system 35 for determining the current power output P from the excore detector currents. The reference values of the core power using the calorimetric measurement, each of the detector currents, and the inlet temperature for each channel are determined at 65 and used to determine Q.sub.wa for each channel. The program then enters a loop 65 in which the current power is determined from the excore detectors periodically. This includes calculation of the relative power for each detector current calculated at 67. The average power is then determined at 69 and output as the excore detector power determination at 71 for each new determination of power. While specific embodiments of the invention have been described in detail, it will be appreciated by those skilled in the art that various modifications and alternatives to those details could be developed in light of the overall teachings of the disclosure. Accordingly, the particular arrangements disclosed are meant to be illustrative only and not limiting as to the scope of invention which is to be given the full breadth of the claims appended and any and all equivalents thereof.