SYSTEM AND METHOD TO DETERMINE REACTIVITY

Abstract

A method of determining reactivity of a nuclear reactor by a reactivity computer may include receiving a neutron detector response for a discrete period of time, performing a statistical check on the neutron detector response, determining if the neutron detector response is acceptable based on the statistical check, and calculating reactivity using a prior delayed neutron concentration if the neutron detector response is not acceptable and using a newly calculated delayed neutron concentration if the neutron detector response is acceptable.

Claims

1. A method of determining reactivity of a nuclear reactor, the method comprising: receiving, by a reactivity computer comprising a processor and a memory, a neutron detector response for a discrete period of time; performing, by the reactivity computer, a statistical check on the neutron detector response; determining, by the reactivity computer, when the neutron detector response is acceptable based on the statistical check; and calculating, by the reactivity computer, a reactivity using a prior delayed neutron concentration when the neutron detector response is not acceptable and using a newly calculated delayed neutron concentration when the neutron detector response is acceptable.

2. The method of claim 1, wherein performing the statistical check comprises determining, by the reactivity computer, when the neutron detector response changes by a predetermined number of standard deviations during the discrete time period, and wherein determining, by the reactivity computer, when the neutron detector response is acceptable comprises determining, by the reactivity computer, that the neutron detector response is acceptable when the neutron detector response changes by less than the predetermined number of standard deviations during the discrete time period and determining that the neutron detector response is not acceptable when the neutron detector response changes by the predetermined number of standard deviations or more during the discrete time period.

3. The method of claim 1, wherein performing, by the reactivity computer, the statistical check comprises determining, by the reactivity computer, when the neutron detector response changes by a predetermined amount during the discrete time period, and wherein determining, by the reactivity computer, when the neutron detector response is acceptable comprises determining that the neutron detector response is acceptable when the neutron detector response changes by less than the predetermined amount during the discrete time period and determining, by the reactivity computer, that the neutron detector response is not acceptable when the neutron detector response changes by the predetermined amount or more during the discrete time period.

4. The method of claim 1, wherein receiving, by a reactivity computer comprising a processor and a memory, a neutron detector response comprises receiving, by the reactivity computer, a response from the neutron detector operating in a first mode or operating in a second mode.

5. The method of claim 4, wherein receiving, by a reactivity computer, a response from the neutron detector operating in a first mode comprises receiving, by a reactivity computer, a response from the neutron detector operating in a pulse mode wherein a plurality of neutron pulses is detected and recorded, and wherein receiving, by a reactivity computer, a response from the neutron detector operating in a second mode comprises receiving, by a reactivity computer, a response from the neutron detector operating in a mean-square voltage mode wherein a pre-amplifier is configured to amplify a plurality of pulse signals and provide a signal proportional to a square root of a reactor power.

6. The method of claim 1, wherein calculating reactivity, by the reactivity computer, comprises calculating, by the reactivity computer, an inverse point kinetics equation to calculate reactivity.

7. A system for calculating reactivity of a reactor core, the system comprising: a neutron detector configured to detect neutron flux produced in the reactor core; and a reactivity computer configured to receive a neutron detector response based on an output of the neutron detector, the reactivity computer comprising a processor and a memory, the memory configured to store a reactivity calculation routine and the processor being configured to execute the reactivity calculation routine, the reactivity routine comprising: receiving, by the reactivity computer, the neutron detector response for a discrete period of time; performing, by the reactivity computer, a statistical check on the neutron detector response; determining, by the reactivity computer, when the neutron detector response is acceptable based on the statistical check; and calculating, by the reactivity computer, a reactivity using a prior delayed neutron concentration when the neutron detector response is not acceptable and using a newly calculated delayed neutron concentration when the neutron detector response is acceptable.

Description

BRIEF DESCRIPTION OF THE DRAWINGS

[0017] A further understanding of the invention can be gained from the following description of the preferred aspects when read in conjunction with the accompanying drawings in which:

[0018] FIG. 1 is a simplified schematic diagram of a nuclear plant;

[0019] FIG. 2A is a schematic top view of a reactor core and associated detectors;

[0020] FIG. 2B is a schematic side view of a reactor core and associated detectors;

[0021] FIG. 3 is a flowchart of a method of determining reactivity in accordance with an example aspect of the disclosed concept;

[0022] FIG. 4 is a chart of a neutron detector signal output and reactivity calculations in accordance with an example aspect of the disclosed concept; and

[0023] FIG. 5 is a simplified schematic diagram of a system for calculating reactivity in accordance with an example aspect of the disclosed concept.

DETAILED DESCRIPTION

[0024] FIG. 3 is a flowchart of a method of determining reactivity in accordance with an example aspect of the disclosed concept. The method eliminates the impact of a step change in detector current when the detector transitions between modes of operation and the output signal is not proportional to reactor power.

[0025] The method begins at 100 and proceeds to 102. At 102, a neutron detector response is received by the reactivity computer. The neutron detector response is received by the reactivity computer over a discrete amount of time such as one second. However, it will be appreciated that any suitable discrete amount of time may be used without departing from the scope of the disclosed concept. In some example aspects of the disclosed concept, the neutron detector may be a fission chamber detector such as that described in U.S. Pat. No. 4,495,144. In some example aspects of the disclosed concept, the neutron detector has two modes of operation: (1) a pulse mode in which neutron pulses are detected and recorded; and (2) a mean-square voltage mode in which a pre-amplifier is used to amplify the pulse signals and provide a signal proportional to the square root of reactor power.

[0026] The method continues at 104 where a statistical check of the neutron detector response is performed by the reactivity computer. In some example aspects of the disclosed concept, the statistical check looks for a jump in the neutron detector response. For example, the statistical check may check whether the neutron detector response changes by a predetermined number of standard deviations e.g., without limitation, two standard deviations) across the discrete time period in which the neutron detector response was received. However, it will be appreciated. that other statistical methods may be used to determine whether the neutron detector response changes by more than a predetermined amount across the discrete time period without departing from the scope of the disclosed concept.

[0027] At 106, the reactivity computer may determine whether the neutron detector response is acceptable. For example, based on the statistic check performed in 104 by the reactivity computer, if the neutron detector response changes by the predetermined number of standard deviations or otherwise changes by more than a predetermined amount, it is determined that the neutron detector response is not acceptable. Such a change is indicative of the neutron detector switching modes and causing a step in its output. If the neutron detector response does not change by the predetermined number of standard deviations or otherwise does not change by more than a predetermined amount, it is determined that the neutron detector response is acceptable.

[0028] If the neutron detector response is determined by the reactivity computer not to be acceptable, the method proceeds to 108 and if the neutron detector response is determined by the reactivity computer to he acceptable, the method proceeds to 110. At 108, the last valid delayed neutron concentration is used in the reactivity calculation. The last valid delayed neutron concentration may be obtained from a previous iteration of the method. For example, if the method runs each discrete time period of one second, the delayed neutron concentration from the previous one second time period may be used if the neutron detector response for that discrete time period was acceptable. At 110, a new delayed neutron concentration is calculated by the reactivity computer. This delayed neutron concentration is considered valid and may be used in a subsequent iteration of the method.

[0029] At 112, reactivity is calculated by the reactivity computer. The reactivity is calculated by the reactivity computer using the last valid delayed neutron concentration if the neutron detector response was not acceptable or using the newly calculated delayed neutron concentration if the neutron detector response was acceptable. In some example aspects, reactivity is calculated by the reactivity computer using an inverse point kinetics equation. An inverse point kinetics equation in accordance with an example aspect of the disclosed concept is provided below.

[00001]$\rho \left(t\right)=\beta -\frac{1}{T\left(t\right)}\underset{i}{.Math.}{\lambda }_i{C}_i\left(t\right)$$\frac{d{C}_i\left(t\right)}{dt}={\beta }_{i}T\left(t\right)-{\lambda }_i{C}_i\left(t\right)$$\text{Where:}{\hat{C}}_i=\Lambda C_i$$T\left(t\right)=\mu DR\left(t\right)$

[0030] In the inverse point kinetics equation: C.sub.i(t) is the delayed neutron concentrations of group i; Λ is the prompt generation time; ρ is the reactivity; the constants β.sub.i and λ.sub.i are the fraction and decay constant of delayed neutron precursor of group i; DR is the magnitude of the detector response signal; and μ is the prompt neutron lifetime.

[0031] The change in neutron detector modes causes a step transition in the neutron detector response which can artificially skew the anticipated neutron population and delayed neutron concentrations in the inverse point kinetics equation. By using the last valid delayed neutron concentration during the step transition, the reactivity computer may eliminate the effect of the step transition on the reactivity calculation. Thus, using the method described above, reactivity can be accurately calculated by the reactivity computer through the change in modes of the neutron detector.

[0032] Once reactivity is calculated at 112, the method returns to 100. The method continually repeats each discrete time period.

[0033] For example, FIG. 4 is a chart of a neutron detector signal output and reactivity calculations in accordance with an example aspect of the disclosed concept. As shown in FIG. 4, the neutron detector output signal 200 generally has a constant upward slope during a positive reactivity addition (i.e., when reactor power is increasing). Conversely, the neutron detector output signal 200 would generally have a constant downward slope when reactor power is decreasing. However, a change in modes of the neutron detector causes a step transition 206. This step transition 206 causes a spike in calculated reactivity using traditional reactivity calculations 202. However, the calculated reactivity using improved calculations 204 eliminates the spike and allows accurate calculation of reactivity through the change in modes of the neutron detector. The improved calculations are those using the method described in connection with FIG. 3. The change in modes of the neutron detector typically occurs during the low power physics testing range and, thus, traditional reactivity calculations cannot be used for low power physics testing, while the improved reactivity calculation can be used to accurately calculate reactivity during low power physics testing of a nuclear reactor. Additionally, the improved reactivity calculation only uses the output signal from one neutron detector rather than multiple neutron detectors.

[0034] FIG. 5 is a simplified schematic diagram of a system for calculating reactivity in accordance with an example aspect of the disclosed concept. The system may implement the method described in connection with FIG. 3. The system includes a neutron detector 200, such as a fission chamber detector, a signal conditioning unit 202, and a reactivity computer 204. The neutron detector 200 detects neutron flux produced in a reactor core and produces electrical current signals proportional to the flux detected. The signal conditioning unit 202 processes the output of the neutron detector 202 processes the output of the neutron detector 200 so that it is suitable for use by the reactivity computer 204.

[0035] The reactivity computer 204 includes a processor 206 and associated memory 208. The memory 208 is structured to store one or more routines and the processor 206 is structured to execute the one or more routines. In some example aspects of the disclosed. concept, the memory 208 stores an improved reactivity calculation routine. The improved reactivity calculation routine may be the method described in connection with FIG. 3, which is executed by the processor 206. Thus, the reactivity computer 204 is able to implement the improved reactivity calculation described in connection with FIG. 3.

[0036] As described herein, example aspects of the disclosed concept provide systems and methods of accurately calculating reactivity through a change in modes of a neutron detector while using the output of just one neutron detector. Example aspects of the disclosed concept are suitable for calculating reactivity in the low power physics testing range of a nuclear reactor.

[0037] While specific aspects 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 and that selected elements of one or more of the example aspects may be combined with one or more elements from other aspects without varying from the scope of the disclosed concepts. Accordingly, the particular aspects disclosed are meant to be illustrative only and not limiting as to the scope of the invention which is to be given the full breadth of the appended claims and any and all equivalents thereof.