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    • 专利摘要:
    A system and method for measuring axial flow for determining sub-criticality in a spent fuel pool of a nuclear installation. At least one neutron detector is used to generate signals resulting from the interactions of neutrons in the pool. A counting device counts the generated signals. A signal analyzer is used to determine the reactivity of the fuel assemblies in the pool based on the counted signals. Software code containing an index of axial flow curves is used to correlate the signals counted to determine the sub-criticality of the spent fuel pool.
    公开号:BE1022456B1
    申请号:E2014/0147
    申请日:2014-03-07
    公开日:2016-04-06
    发明作者:Ho Q. Lam；Vefa N. Kucukboyaci；Yung-An Chao；Robert W. Flammang；William H. Slagle；Patrick J. Sebastiani
    申请人:Westinghouse Electric Company Llc；
    IPC主号:
    专利说明:

    SYSTEMS AND METHODS FOR MEASURING AND MONITORING SUB-CRITICITY OF FUEL POOL USE Cross-reference to related applications
    The present application includes a priority claim based on Section 35 U.S.C. Section 119 (e) of Provisional Application 61/792 334, entitled "Systems and Metrics for Sphere Fuel Pool Sübcriticality Measurement and Monitoring" filed March 15, 2013.
    CONTEXT
    Field
    The present invention generally relates to spent fuel pools in nuclear facilities and, more particularly, to systems and methods for measuring and monitoring axial flow to evaluate sub-criticality in a spent fuel pool.
    Description of the Related Art
    The generation of electrical energy in a nuclear facility is accomplished by the nuclear fission of radioactive materials. Because of the volatility of the nuclear response, nuclear facilities must in practice be designed in such a way that the health and safety of people is ensured. - In conventional nuclear facilities used to generate electrical energy, the nuclear fuel becomes irradiated and is removed at periodic intervals from the nuclear reactor and replaced with new fuel. The spent fuel generates a decay heat and remains radioactive after being removed from the nuclear reactor. Thus, a secure storage facility is provided for receiving the spent fuel. In nuclear reactors, such as pressurized water reactors, a pool is provided as a storage pool for spent fuel. The spent fuel pool is designed to contain a water level such that spent fuel is stored under water. The used fuel pool is usually constructed of concrete and has a depth of at least 40 feet. In addition to monitoring and monitoring the water level, water quality is also monitored and monitored to prevent fuel degradation while in the spent fuel pool. In addition, the water in the spent fuel pool is continuously cooled to extract the heat that is produced by the spent fuel.
    A pool of spent fuel in a nuclear facility usually consists of several fuel assembly storage racks filled with either depleted or new fuel assemblies. The reactivity of the pool is expressed by an effective factor of neutron multiplication, k-effective. The value of k-effective is generally determined by analytical means, for example by the use of Monte Carlo simulations.
    The known storage configurations in the spent fuel pool may include a compact checkerboard configuration with empty water cells, and with or without neutron absorbers. The storage configuration chosen depends on the responsiveness of the depleted assemblies. The storage configuration is chosen to ensure that the overall responsiveness of the pool remains below regulatory limits.
    Monitoring and control of the subcritical margin in the spent fuel pool can ensure safe operation of the pool. This information is known to be obtained by analytical methods that are based on conventional input assumptions to encompass a wide range of core operating parameters for depleted fuel assemblies. As a result, a considerable amount of subcritical margin may exist in the spent fuel pool based on the analytical results.
    Due to a lack of reprocessing and a shortage of permanent disposal sites, commercial nuclear facilities are interested in systems and processes to increase storage capacity as some nuclear facilities are operating at near full capacity. the spent fuel pool. Larger initial enhancements in compact storage configurations and degradation issues with reactivity control materials are some of the factors that make up the uncertainty associated with the responsiveness of pools and, as a result, create regulatory problems as to the safe operation of spent fuel pools.
    Thus, there is a desire in the nuclear energy industry to develop a system and method for measuring the k-workforce with greater certainty and a smaller margin so as to obtain at least one of the following advantages (1) an increase in the amount of soluble boron that can be credited, thereby effectively increasing storage capacity, reducing the number of different and complex storage configurations, and simplifying compliance with technical specifications, and (2) elimination of regulatory issues regarding uncertainties as to whether there is sufficient margin for criticality or whether regulatory limits are met.
    The present invention addresses the problems described above by providing systems and methods for measuring and monitoring the margin of sub-criticality in the spent fuel pool that is based on measuring the axial flow in the spent fuel pool, generating an axial flow curve and correlate the curve with analytical data to determine the k-effective and monitor any changes in reactivity, for example inadvertently and anticipated, in the spent fuel pool.
    ABSTRACT
    In one aspect, the present invention provides a system for measuring and monitoring an axial flow to determine sub-criticality in a spent fuel pool of a nuclear facility. The system includes: a neutron source located in the spent fuel pool; an analytical tool for generating analytical axial flow curves for a plurality of different concentrations of soluble boron, generating an axial axial flow curve index based on analytical axial flow curves, determining a slope for each of the analytical axial flow curves and determine an effective neutron multiplication factor based on the slope; one or more neutron detectors installed in the spent fuel pool and arranged to generate signals resulting from neutron interactions in the spent fuel pool; a counting device for counting said signals generated by said one or more neutron detectors; connection means for electrically connecting said one or more neutron detectors to the counting device; a signal analyzer for receiving counted signals from the counting device; a computer coupled to the signal analyzer and arranged to store the axial axial flow curve index, generate a measured axial flow curve, determine a slope of the measured axial flow curve and correlate the slope of the flow curve axial measured with the index of axial axial flow curves to obtain a value of an effective multiplication factor measured; and a power supply for the neutron detectors, the counting device and the signal analyzer.
    In another aspect, the present invention provides a method for measuring and monitoring an axial flow to evaluate sub-criticality in a spent fuel pool of a nuclear facility. The method comprises: the analytical determination of the most reactive regions of the spent fuel pool; the analytical generation of an analytical axial flow curve for a plurality of different soluble boron concentrations; the analytical generation of an index of analytical axial flow curves based on analytical axial flow curves; storing the analytical axial flow curve index on a computer; the analytical determination of a slope for each of the analytical axial flow curves; the analytical determination of an effective neutron multiplication factor based on the slope; the installation of one or more neutron detectors in the spent fuel pool; generating, by the neutron detector (s), signals resulting from neutron interactions in the spent fuel pool; the electrical connection of the one or more neutron detectors with a counting device for counting the signals generated by the one or more neutron detectors; receiving counted signals from the counting device; generating an axial flux curve measured on the basis of the counted signals; determining a slope of the measured axial flow curve; and correlating the slope of the measured axial flux curve with the analytical axial flow curve index to obtain a value of an effective multiplication factor measured. BRIEF DESCRIPTION OF THE DRAWINGS A more complete understanding of the invention can be obtained from the following description of the preferred embodiments when read in conjunction with the accompanying drawings, in which:
    Figure 1 shows traced curves of the Monte Carlo simulation results for a set of depleted fuel assemblies stored in a spent fuel pool, according to some embodiments of the present invention.
    Fig. 2 is a diagram showing the components of a spent fuel pool measuring and monitoring system, according to some embodiments of the present invention.
    DETAILED DESCRIPTION OF PREFERRED EMBODIMENTS
    The present invention provides systems and methods for measuring and monitoring an axial flow in a spent fuel pool of a nuclear facility to evaluate the degree of sub-criticality in the spent fuel pool. Generally, the systems and methods of the present invention evaluate the degree of subcriticality using the shape of the axial flow distribution in the presence of a neutron source. The measurement system includes neutron detectors, a signal analysis system and a neutron source in the spent fuel pool. The signal analysis system contains a correlation curve for the index of axial shapes with respect to the degree of subcriticality.
    In some embodiments, the nuclear facility is a pressurized water reactor. A conventional spent fuel pool in a nuclear facility, such as a pressurized water reactor, consists of several hundred fuel assembly storage racks filled with either depleted or new fuel assemblies. The reactivity of the spent fuel pool is expressed by the effective neutron multiplication factor, k-effective, and is controlled by various means, such as, for example, a high concentration of water-soluble boron in the pool of water. spent fuel and other fixed or mobile neutron absorption devices that act as neutron absorbers to maintain reactivity. Neutron absorbing devices may include boric stainless steel racks, boral panels, and Metamic inserts.
    The fuel assemblies can be stored in the spent fuel pool in various configurations, such as checkerboard and compact with empty water cells, with or without neutron absorbers. The particular configuration used depends on the responsiveness of the depleted assemblies. The reactivity of the depleted assemblies may depend on the initial enrichment, nuclear combustion, depletion history, and cooling period (for example, the time after reactor core discharge). The storage configuration is chosen with the objective of ensuring that the overall reactivity of the spent fuel pool remains below regulatory limits. In the United States, the Nuclear
    Regulatory Commission (NRC) establishes specifications for the safe operation of nuclear facilities. Currently, the NRC specifications are that the k-strength of the spent fuel pool should not exceed 0.95 under normal conditions and that the k-effective must remain below 1.0 in the absence of soluble boron. , if the presence of soluble boron is part of the normal operating conditions.
    In general, the amount or degree of subcriticality of the spent fuel pool is useful in estimating whether the spent fuel pool is operating and maintained in a safe condition. Generally, this information is obtained by analytical methods that are based on very conventional input assumptions to encompass a wide range of core operating parameters with which the fuel assemblies can be depleted. As a result, a considerable amount of subcritical margin may exist in the spent fuel pool. In particular, in the presence of high concentrations of soluble boron.
    Without being limited by any particular theory, it is believed that the determination and evaluation of the amount or degree of sub-criticality of the spent fuel pool using systems and methods that utilize measured values (e.g. axial flow measurements) focused on the actual operating parameters will provide advantages over known conventional systems and methods. For example, at least one of the following advantages can be achieved by generating a measured value of k-effective: (1) increasing the amount of soluble boron that can be credited, effectively increasing the storage capacity, reduces the number of different and complex storage configurations, and simplifies compliance with technical specifications, and (2) eliminates regulatory issues regarding uncertainties as to whether there is sufficient margin for criticality or whether the regulatory limits are met.
    In the present invention, measurement and monitoring systems and methods that are based on the sensitivity of the flux form to the degree of subcriticality are used to determine the k-effective and evaluate any variations in reactivity (by example, inadvertently and anticipated) in the spent fuel pool. In general, the axial flow in the environment of the spent fuel pool is measured so that a degree of subcriticality can be determined or deduced therefrom.
    Various methods and devices for measuring axial flow in a spent fuel pool are known in the art. These known and conventional methods and devices are suitable for use in the present invention. In the present invention, the axial flow is measured in the more reactive regions of the spent fuel pool because, without wishing to be bound by any particular theory, it is believed that the k-effective of the spent fuel pool is controlled by the most reactive region of the spent fuel pool and, therefore, the degree of subcriticality can be deduced based on the measurement of the axial flow in the most reactive fuel assembly.
    In some embodiments, for example, in a pressurized water reactor, the upper portion of a depleted fuel assembly is significantly less consumed than the middle portion due to the axial power and moderator density profiles during operation. impoverishment. When the depleted assembly is placed in the spent fuel pool, a major part of the contribution to reactivity will result from the top of the assembly. The most reactive regions can be determined using various methods and devices known in the art. In some embodiments, the most reactive regions are determined by simulations, for example using a Monte Carlo analysis. The existence of a neutron flux in a subcritical spent fuel pool is maintained by external neutron sources in the pool. Without wishing to be bound by any particular theory, it is thought that when there is a significant margin of sub-criticality in the spent fuel pool, for example, the pool is not close to criticality, the axial flow will depend on the external source (in addition to the small amount of spontaneous fission source). When there is a small margin of subcriticality in the spent fuel pool, for example, the pool is about to approach criticality, the axial flow varies as the number of neutrons from the reaction fissions induced chain increases and begins to control the axial flow. This behavior is demonstrated in Figure 1 which shows the results of Monte Carlo simulations for a set of depleted fuel assemblies stored in the spent fuel pool. In this configuration of assemblies, a fixed neutron source provides a constant flux of neutrons around the median plane of the fuel assembly. The sub-criticality of the spent fuel pool is modified by changing either the soluble boron concentration or the configuration of the spent fuel pool. For purposes of illustration, axial flow measurements were taken in the spent fuel pool at various concentrations of soluble boron, particularly 1500 ppm, 1600 ppm, 1700 ppm, 1800 ppm and 2.400 ppm. These measurements were plotted to generate a curve or shape of the axial flow for each of the soluble boron concentrations. As can be seen in FIG. 1, the shape of the axial flow has a central peak due to the fixed neutron source in a very subcritical pool (for example, a high boron concentration of 2,400 ppm). As the spent fuel pool approaches criticality, the fission reactions induced in the upper parts of the assembly begin to generate more neutrons than the fixed source, thereby deflecting the shape of the axial flux. The upper parts of the assembly are highly under-consumed and, therefore, more reactive.
    In some embodiments, axial flow measurements are taken in the spent fuel pool at various concentrations of soluble boron. The measurements are plotted for each of the soluble boron concentrations and curves or shapes are generated such that each boron concentration has a curve or an axial flow form associated therewith. Plotting data to obtain a curve or shape can be done manually or using an electronic device. The slope of these curves or shapes can be determined using conventional methods and devices known in the art.
    In addition, curves or forms of axial flow for a spent fuel pool can be obtained analytically for selected soluble boron concentrations using analytical tools such as Monte Carlo analysis (eg, simulation). As a result, an index of curves or axial shapes can be generated. The slope of curves or analytic forms can be determined using analytical tools. The value of the slope can be used to obtain a value of k-effective.
    The curves or forms derived from the measured axial flow data can be correlated with the index of curves or axial flow shapes deduced from analytical data. For example, the slope of the curve or shape deduced from the measured axial flow can be correlated with the slope of the index of curves or shapes of axial flue. As a result of this correlation, a value of k-effective for each of the curves or forms of measured axial flow is obtained.
    According to some embodiments of the invention, the following simplified analysis analytically demonstrates flow behavior in a subcritical system in the presence of an external source. The following cases are examined: (I) a mono-group and one-dimensional homogeneous medium without chain reaction fission and (II) a mono-group and unidimensional homogeneous medium with a chain reaction fission. I. Analysis without chain reaction fission term The diffusion equation for this point source analysis at x = 0 is -D (d2 <p / dx2) + Zacp = S5 (x) (1).
    The shape of the flux is given by the solution of the equation remote from the location of the source -D (d2cp / dx2) + Iacp = 0 (2).
    In terms of the diffusion length, L, equation 2 can be rewritten as -L2 (d2cp / dx2) + φ = 0 (3) where
    (4).
    The solution of equation 3 is the simple exponential function in equation 5, its amplitude being fixed by the intensity of the source in equation 1 <p (x) = SL / 2D exp (-x / L) (5). II. Analysis with chain reaction fission term Analysis I above is modified by adding the chain reaction fission term as follows -D (d2 <p / dx2) + Ia (p = Σ / φ + Sö (x) (6) Equation 6 can be written as -D (d2 <p / dx2) + la (1 -I (Æa) φ = Sö (x) (7).
    In terms of the multiplication factor, k, or sub-criticality (1-k), equation 7 can be rewritten as -Dfcftp / dx2) + Ia (1-k) <p = S5 (x) (8) where k = Σ fÆa (9) and
    (4).
    The comparison of equation 8 with equation 1 shows that the absorption section is multiplied by the sub-criticality factor (1-k) and, therefore, the flux distribution in equation 5 is modified by corresponding manner in the following general form cp (x) = (SL / 2D V (1-3) exp (-x V (V ^ / L)) (10) The equation above demonstrates how the exponential varies With the subcriticality, the more the spent fuel pool becomes critical, the steeper the exponential slope, and as the spent fuel pool approaches criticality, the flow distribution approaches a flat constant that is the fundamental mode for a homogeneous medium.
    In some embodiments, the methods and systems of the present invention include a neutron detector system installed in the spent fuel pool. The neutron detector system may be selected from those known in the art and commercially available. Neutron detector systems for use in the present invention include systems that are capable of operating in the spent fuel pool environment. The neutron detector system includes one or more neutron detectors that can be used for and that are capable of generating signals as a result of the detection of the neutron interaction in the spent fuel pool. It is preferred that the neutron detector be of relatively small size so that it can be mounted among and around the fuel storage racks. In particular, a plurality of neutron detectors are installed in the most reactive regions in the spent fuel pool. In some embodiments, each of the neutron detectors comprises at least one silicon carbide (SiC) semiconductor diode and associated electronics. An SiC detector is generally compact. For example, the detector diameter may be about 1 inch. In addition, the SiC detector is capable of operating at elevated temperatures (above about 500 ° C) and in high radiation fields (about 50,000 R / H). In addition, one of the key features of the SiC detector is its ability to operate in a neutron pulse mode when exposed to high gamma-ray fields.
    A counting device or counting electronics is provided, which can be used for and is able to count the signals that are generated by said one or more neutron detectors. The neutron detector and the counting device or the counting electronics are electrically connected or chopped by connection means or mechanism such as, but not limited to, a cable which transfers the signals counted by the counting device or the counting electronics. The counted signals are received as input to a signal analyzer. The signal analyzer can be used for and is able to determine the reactivity of the fuel assemblies in the spent fuel pool based on the counted signals. These components are connected to or coupled to a computer system that includes a software program, such as a computer code, that contains an index of curves or axial flow shapes. This index is based on analytical or predetermined data. The software program can be used for and is able to correlate the counted signals with the index of curves or axial flow shapes to evaluate the sub-criticality of the spent fuel pool.
    Additional equipment includes a high voltage power supply for powering the neutron detector system and a power supply for the counting device or the counting electronics.
    In some embodiments, in a spent fuel pool of a nuclear facility, one or more SiC diodes are mounted in a watertight housing. In the housing, the SiC diode is electrically connected to a watertight cable that transfers signals resulting from neutron interactions into the spent fuel pool to one or more electronic meters. The signal pulses will be counted and the count rate determined by a computer, which will then determine and display the reactivity of the fuel assemblies in the spent fuel pool.
    Figure 2 is a schematic of a spent fuel pool sub-criticality measurement and monitoring system according to some embodiments of the present invention. As shown in Figure 2, a sensing device measures neutron reactions in the spent fuel pool and generates electrical signals therefrom. A counting device receives and counts the electrical signals generated by the detection device. A signal analyzer receives the counted signals, produces purified signals, and determines the measured reactivity of the fuel assemblies in the spent fuel pool. The signal analyzer includes a bias / voltage separation circuit box, an amplifier, a discriminator, and a computer. The bias circuit / voltage separation box, the amplifier and the discriminator can be used to purify the counted signals. The purified signals are then received by the computer as an input. The computer also receives analytical data entered by the user, such as, for example, pool-specific operating parameters. The computer uses a software program containing an index of curves or axial flow shapes. The purified signals are correlated with the index of curves or axial flow shapes. As a result of this correlation, the measured reactivity of the spent fuel pool is obtained for use in assessing the sub-criticality of the pool. In addition, the spent fuel pool sub-criticality measurement and monitoring system shown in Figure 2 includes a power supply.
    Although specific embodiments of the invention have been described in detail, those skilled in the art will appreciate that various modifications and variations of these details could be developed in light of the overall teachings of the presentation. Therefore, the particular embodiments presented are intended to be illustrative only and not limiting as to the scope of the invention which is to receive the full scope of the appended claims and all equivalents thereof.
    权利要求:
    Claims (9)
    [1]
    1. Axial flow measurement and monitoring system for determining the undercapacity in a spent fuel pool of a nuclear facility, which includes: a neutron source located in the spent fuel pool; an analytical tool for generating analytical axial flow curves for a plurality of different concentrations of borated boron, generating an axial axial flow curve index based on analytical axial flow curves, determining a slope for each of the analytical axial flow curves and determine an effective neutron multiplication factor based on the slope; one or more neutron detectors installed in the spent fuel pool and arranged to generate signals resulting from neutron interactions in the spent fuel pool; a counting device for counting said signals generated by said one or more neutron detectors; connection means for electrically connecting said one or more neutron detectors to the counting device; a signal analyzer for receiving counted signals from the counting device; a computer coupled to the signal analyzer and arranged to store the axial axial flow curve index, generate a measured axial flow curve, determine a slope of the measured axial flow curve and correlate the slope of the flow curve axial measured with the index of axial axial flow curves to obtain a value of an effective multiplication factor measured; and a power supply for the neutron detectors, the counting device and the signal analyzer.
    [2]
    The system of claim 1, wherein said one or more neutron detectors comprise at least one silicon carbide semiconductor diode.
    [3]
    3. System according to claim 1, wherein the nuclear installation is a pressurized water reactor.
    [4]
    The system of claim 1, wherein the effective multiplication factor is less than or equal to 0.95 under normal conditions.
    [5]
    The system of claim 1, wherein the effective multiplication factor is less than 1.0% soluble boron salt and including the presence of soluble boron in a normal operating condition.
    [6]
    The system of claim 1, wherein the axial flow is measured in regions of the spent fuel pool having the highest reactivity.
    [7]
    The system of claim 6, wherein regions of the spent fuel pool having the highest reactivity are determined by Monte Carlo simulations and the analytical axial flow curve index is generated using Monte Carlo simulations. .
    [8]
    A method for measuring and monitoring axial flow to determine sub-criticality in a spent fuel pool of a nuclear facility, comprising: the analytical determination of the most reactive regions of the spent fuel pool; the analytical generation of an analytical axial flow curve for a plurality of different soluble boron concentrations; the analytical generation of an index of analytical axial flow curves based on analytical axial flow curves; storing the analytical axial flow curve index on a computer; the analytical determination of a slope for each of the analytical axial flow curves; the analytical determination of an effective neutron multiplication factor based on the slope; the installation of one or more neutron detectors in the spent fuel pool; generating, by the neutron detector (s), signals resulting from neutron interactions in the spent fuel pool; the electrical connection of the one or more neutron detectors with a counting device for counting the signals generated by the one or more neutron detectors; receiving counted signals from the counting device; generating an axial flux curve measured on the basis of the counted signals; determining a slope of the measured axial flow curve; and correlating the slope of the measured axial flux curve with the analytical axial flow curve index to obtain a value of an effective multiplication factor measured.
    [9]
    The method of claim 8, wherein the analytical generation of an analytical axial flow curve index based on analytical axial flow curves uses Monte Carlo simulations.
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    引用文献:
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    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    US201361792334P| true| 2013-03-15|2013-03-15|
    US61/792334|2013-03-15|
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