COVARIANCE DATA CREATION APPARATUS, REACTOR CORE ANALYSIS APPARATUS, COVARIANCE DATA CREATION METHOD, MACROSCOPIC COVARIANCE ADJUSTMENT METHOD, REACTOR CORE CHARACTERISTIC EVALUATION METHOD, COVARIANCE DATA CREATION PROGRAM, MACROSCOPIC COVARIANCE ADJUSTMENT PROGRAM, AND REACTOR CORE CHARACTERISTIC EVALUATION PROGRAM

Abstract

A covariance data creation apparatus configured to execute assembly calculations on a fuel assembly based on microscopic cross sections, the apparatus executing: a perturbation data generation step of deriving a plurality of perturbation quantities of the microscopic cross sections based on microscopic covariance data that is data regarding uncertainties of the microscopic cross sections, and generating microscopic perturbation data from the derived perturbation quantities of the microscopic cross sections; a macroscopic cross section derivation step of executing the assembly calculations based on the microscopic perturbation data generated at the perturbation data generation step, and deriving a plurality of macroscopic cross sections individually corresponding to the perturbation quantities of the microscopic cross sections; and a macroscopic covariance data generation step of generating macroscopic covariance data that is data regarding uncertainties of the macroscopic cross sections based on the macroscopic cross sections derived at the macroscopic cross section derivation step.

Claims

1. A covariance data creation apparatus comprising a first arithmetic unit configured to execute assembly calculations on a fuel assembly based on microscopic cross sections, the first arithmetic unit executing: a perturbation data generation step of deriving a plurality of perturbation quantities of the microscopic cross sections based on microscopic covariance data that is data regarding uncertainties of the microscopic cross sections, and generating microscopic perturbation data from the derived perturbation quantities of the microscopic cross sections; a macroscopic cross section derivation step of executing the assembly calculations based on the microscopic perturbation data generated at the perturbation data generation step, and deriving a plurality of macroscopic cross sections individually corresponding to the perturbation quantities of the microscopic cross sections; and a macroscopic covariance data generation step of generating macroscopic covariance data that is data regarding uncertainties of the macroscopic cross sections based on the macroscopic cross sections derived at the macroscopic cross section derivation step.

2. The covariance data creation apparatus according to claim 1, wherein as a calculation condition for executing the assembly calculations based on the microscopic perturbation data, a predetermined parameter as a representative is previously selected as a representative parameter from parameters regarding a reactor core state of a reactor core including the fuel assembly, and at the macroscopic cross section derivation step, the assembly calculations based on the microscopic perturbation data are executed using the selected representative parameter as the calculation condition.

3. A reactor core analysis apparatus comprising a second arithmetic unit configured to execute core calculations on a reactor core based on the macroscopic cross sections by using the macroscopic covariance data created by the covariance data creation apparatus according to claim 1, perturbation quantities of the macroscopic cross sections derived based on the macroscopic covariance data being previously generated as macroscopic perturbation data, the second arithmetic unit executing: a reactor core characteristic derivation step of executing the core calculations based on the macroscopic perturbation data, and deriving a plurality of reactor core characteristics individually corresponding to the perturbation quantities of the macroscopic cross sections; a sensitivity data acquisition step of acquiring a relation between a change in the macroscopic cross sections and a change in the reactor core characteristics accompanying the change in the macroscopic cross sections, as sensitivity data; a measurement data acquisition step of acquiring reactor core characteristics of the reactor core measured by a measurement apparatus measuring the reactor core characteristics, as reactor core characteristic measurement data; an adjustment quantity derivation step of deriving an adjustment quantity of the macroscopic covariance data from a predetermined equation based on the sensitivity data; and an adjusted macroscopic covariance derivation step of deriving adjusted macroscopic covariance data adjusted based on the adjustment quantity derived at the adjustment quantity derivation step.

4. The reactor core analysis apparatus according to claim 3, wherein perturbation quantities of the macroscopic cross sections derived based on the adjusted macroscopic covariance data are previously generated as adjusted macroscopic perturbation data, and the second arithmetic unit further executes: a reactor core characteristic derivation step of executing the core calculations based on the adjusted macroscopic perturbation data, and deriving a plurality of reactor core characteristics individually corresponding to the perturbation quantities of the macroscopic cross sections; and a reactor core characteristic covariance data generation step of generating reactor core characteristic covariance data that is data regarding uncertainties of the reactor core characteristics based on the reactor core characteristics derived at the reactor core characteristic derivation step.

5. A covariance data creation method of generating macroscopic covariance data that is data regarding uncertainties of macroscopic cross sections obtained as output values of assembly calculations on a fuel assembly by a covariance data creation apparatus configured to execute the assembly calculations on the fuel assembly based on microscopic cross sections, the covariance data creation method executing: a perturbation data generation step of deriving a plurality of perturbation quantities of the microscopic cross sections based on microscopic covariance data that is data regarding uncertainties of the microscopic cross sections, and generating microscopic perturbation data from the derived perturbation quantities of the microscopic cross sections; a macroscopic cross section derivation step of executing the assembly calculations based on the microscopic perturbation data generated at the perturbation data generation step, and deriving a plurality of macroscopic cross sections individually corresponding to the perturbation quantities of the microscopic cross sections; and a macroscopic covariance data generation step of generating the macroscopic covariance data based on the macroscopic cross sections derived at the macroscopic cross section derivation step.

6. A macroscopic covariance adjustment method of adjusting macroscopic covariance data that is data regarding uncertainties of macroscopic cross sections by a reactor core analysis apparatus configured to execute core calculations on a reactor core based on the macroscopic cross sections, perturbation quantities of the macroscopic cross sections derived based on the macroscopic covariance data being previously generated as macroscopic perturbation data, the method macroscopic covariance adjustment executing: a reactor core characteristic derivation step of executing the core calculations based on the macroscopic perturbation data, and deriving a plurality of reactor core characteristics individually corresponding to the perturbation quantities of the macroscopic cross sections; a sensitivity data acquisition step of acquiring a relation between a change in the macroscopic cross sections and a change in the reactor core characteristics accompanying the change in the macroscopic cross sections, as sensitivity data; a measurement data acquisition step of acquiring reactor core characteristics of the reactor core measured by a measurement apparatus measuring the reactor core characteristics, as reactor core characteristic measurement data; an adjustment quantity derivation step of deriving an adjustment quantity of the macroscopic covariance data from a predetermined equation based on the sensitivity data; and an adjusted macroscopic covariance derivation step of deriving adjusted macroscopic covariance data adjusted based on the adjustment quantity derived at the adjustment quantity derivation step.

7. A reactor core characteristic evaluation method of evaluating reactor core characteristics of a reactor core by a reactor core analysis apparatus configured to evaluate the reactor core characteristics of the reactor core by executing core calculations on the reactor core based on macroscopic cross sections, perturbation quantities of the macroscopic cross sections derived based on the adjusted macroscopic covariance data derived by the macroscopic covariance adjustment method according to claim 6 being previously generated as adjusted macroscopic perturbation data, the reactor core characteristic evaluation method executing: a reactor core characteristic derivation step of executing the core calculations based on the adjusted macroscopic perturbation data, and deriving a plurality of reactor core characteristics individually corresponding to the perturbation quantities of the macroscopic cross sections; and a reactor core characteristic covariance data generation step of generating reactor core characteristic covariance data that is data regarding uncertainties of the reactor core characteristics based on the reactor core characteristics derived at the reactor core characteristic derivation step.

8. A covariance data creation program executed by a covariance data creation apparatus configured to execute assembly calculations on a fuel assembly based on microscopic cross sections, the covariance data creation program comprising: a perturbation data generation step of deriving a plurality of perturbation quantities of the microscopic cross sections based on microscopic covariance data that is data regarding uncertainties of the microscopic cross sections, and generating microscopic perturbation data from the derived perturbation quantities of the microscopic cross sections; a macroscopic cross section derivation step of executing the assembly calculations based on the microscopic perturbation data generated at the perturbation data generation step, and deriving a plurality of macroscopic cross sections individually corresponding to the perturbation quantities of the microscopic cross sections; and a macroscopic covariance data generation step of generating macroscopic covariance data that is data regarding uncertainties of the macroscopic cross sections based on the macroscopic cross sections derived at the macroscopic cross section derivation step.

9. A macroscopic covariance adjustment program executed by a reactor core analysis apparatus configured to execute core calculations on a reactor core based on macroscopic cross sections, perturbation quantities of the macroscopic cross sections derived based on macroscopic covariance data that is data regarding uncertainties of the macroscopic cross sections being previously generated as macroscopic perturbation data, the macroscopic covariance adjustment program comprising: a reactor core characteristic derivation step of executing the core calculations based on the macroscopic perturbation data, and deriving a plurality of reactor core characteristics individually corresponding to the perturbation quantities of the macroscopic cross sections; a sensitivity data acquisition step of acquiring a relation between a change in the macroscopic cross sections and a change in the reactor core characteristics accompanying the change in the macroscopic cross sections, as sensitivity data; a measurement data acquisition step of acquiring reactor core characteristics of the reactor core measured by a measurement apparatus measuring the reactor core characteristics, as reactor core characteristic measurement data; an adjustment quantity derivation step of deriving an adjustment quantity of the macroscopic covariance data from a predetermined equation based on the sensitivity data; and an adjusted macroscopic covariance derivation step of deriving adjusted macroscopic covariance data adjusted based on the adjustment quantity derived at the adjustment quantity derivation step.

10. A reactor core characteristic evaluation program executed by a reactor core analysis apparatus configured to execute core calculations on a reactor core based on macroscopic cross sections, perturbation quantities of the macroscopic cross sections derived based on the adjusted macroscopic covariance data derived by the macroscopic covariance adjustment program according to claim 9 being previously generated as adjusted macroscopic perturbation data, the reactor core characteristic evaluation program comprising: a reactor core characteristic derivation step of executing the core calculations based on the adjusted macroscopic perturbation data, and deriving a plurality of reactor core characteristics individually corresponding to the perturbation quantities of the macroscopic cross sections; and a reactor core characteristic covariance data generation step of generating reactor core characteristic covariance data that is data regarding uncertainties of the reactor core characteristics based on the reactor core characteristics derived at the reactor core characteristic derivation step.

11. A reactor core analysis apparatus comprising an arithmetic unit configured to execute core calculations on a reactor core based on the macroscopic cross sections by using macroscopic covariance data that is data regarding uncertainties of macroscopic cross sections, the arithmetic unit executing: a sensitivity data acquisition step of acquiring a relation between a change in the macroscopic cross sections and a change in the reactor core characteristics accompanying the change in the macroscopic cross sections, as sensitivity data; a measurement data acquisition step of acquiring reactor core characteristics of the reactor core measured by a measurement apparatus measuring the reactor core characteristics, as reactor core characteristic measurement data; an adjustment quantity derivation step of deriving an adjustment quantity of the macroscopic covariance data from a predetermined equation based on the sensitivity data; and an adjusted macroscopic covariance derivation step of deriving adjusted macroscopic covariance data adjusted based on the adjustment quantity derived at the adjustment quantity derivation step.

12. A macroscopic covariance adjustment method of adjusting macroscopic covariance data that is data regarding uncertainties of macroscopic cross sections by a reactor core analysis apparatus configured to execute core calculations on a reactor core based on the macroscopic cross sections, the method macroscopic covariance adjustment executing: a sensitivity data acquisition step of acquiring a relation between a change in the macroscopic cross sections and a change in the reactor core characteristics accompanying the change in the macroscopic cross sections, as sensitivity data; a measurement data acquisition step of acquiring reactor core characteristics of the reactor core measured by a measurement apparatus measuring the reactor core characteristics, as reactor core characteristic measurement data; an adjustment quantity derivation step of deriving an adjustment quantity of the macroscopic covariance data from a predetermined equation based on the sensitivity data; and an adjusted macroscopic covariance derivation step of deriving adjusted macroscopic covariance data adjusted based on the adjustment quantity derived at the adjustment quantity derivation step.

13. A macroscopic covariance adjustment program executed by a reactor core analysis apparatus configured to execute core calculations on a reactor core based on macroscopic cross sections, the macroscopic covariance adjustment program comprising: a sensitivity data acquisition step of acquiring a relation between a change in the macroscopic cross sections and a change in the reactor core characteristics accompanying the change in the macroscopic cross sections, as sensitivity data; a measurement data acquisition step of acquiring reactor core characteristics of the reactor core measured by a measurement apparatus measuring the reactor core characteristics, as reactor core characteristic measurement data; an adjustment quantity derivation step of deriving an adjustment quantity of the macroscopic covariance data from a predetermined equation based on the sensitivity data; and an adjusted macroscopic covariance derivation step of deriving adjusted macroscopic covariance data adjusted based on the adjustment quantity derived at the adjustment quantity derivation step.

Description

BRIEF DESCRIPTION OF DRAWINGS

[0021] FIG. 1 is a schematic configuration diagram schematically illustrating a covariance data creation apparatus according to the present embodiment.

[0022] FIG. 2 is a schematic configuration diagram schematically illustrating a reactor core analysis apparatus according to the present embodiment.

[0023] FIG. 3 is an explanatory view schematically illustrating a reactor core as an analysis target.

[0024] FIG. 4 is a cross-sectional view of a fuel assembly as an analysis target cut along a plane perpendicular to an axial direction.

[0025] FIG. 5 is a flowchart regarding creation of unadjusted macroscopic covariance data.

[0026] FIG. 6 is a flowchart regarding adjustment of macroscopic covariance.

[0027] FIG. 7 is a flowchart regarding creation of reactor core characteristic covariance data.

DESCRIPTION EMBODIMENTS

[0028] Hereinafter, an embodiment according to the present invention will be described in detail based on the drawings. Note that the embodiment is not intended to limit the present invention. Additionally, components in the following embodiment include components replaceable and easily conceivable by a person skilled in the art or components substantially identical therewith. Furthermore, the following components can be combined together as appropriate, and when there are a plurality of embodiments, the respective embodiments can be combined together.

Present Embodiment

[0029] A covariance data creation apparatus 10 and a reactor core analysis apparatus 20 according to the present embodiment are used for nuclear design calculation. The covariance data creation apparatus 10 is an apparatus configured to perform assembly calculations using microscopic cross sections as input values to generate covariance data of macroscopic cross sections used as input values for core calculations. Additionally, the reactor core analysis apparatus 20 is an apparatus configured to perform core calculations using the macroscopic cross sections as input values to generate values regarding characteristics of a reactor core (hereinafter, simply referred to as reactor core characteristics) as output values.

[0030] FIG. 1 is a schematic configuration diagram schematically illustrating the covariance data creation apparatus according to the present embodiment. The covariance data creation apparatus 10 includes a first arithmetic unit 11 configured to carry out arithmetic operations by executing various computer programs, a first storage unit 12 configured to store various computer programs and data, a first input unit 13 formed of an input device such as a keyboard, and a first output unit 14 formed of an output device such as a monitor. Note that the covariance data creation apparatus 10 may be formed of a single apparatus, an apparatus integrated with the reactor core analysis apparatus 20, or a plurality of apparatuses combining an arithmetic apparatus, a data server or the like, and is not limited to a particular configuration.

[0031] The first storage unit 12 stores various computer programs such as a lattice calculation code C1 used for calculating the macroscopic cross sections and a covariance data creation program P1 used for creating the macroscopic covariance data. The first storage unit 12 also stores data such as a cross section library collecting the cross sections, the macroscopic cross sections derived by the assembly calculations, and the macroscopic covariance data derived based on the macroscopic cross sections.

[0032] FIG. 2 is a schematic configuration diagram schematically illustrating the reactor core analysis apparatus. As illustrated in FIG. 1, the reactor core analysis apparatus 20 includes a second arithmetic unit 21 configured to carry out arithmetic operations by executing various computer programs, a second storage unit 22 configured to store various computer programs and data, a second input unit 23 formed of an input device such as a keyboard, and a second output unit 24 formed of an output device such as a monitor. Note that the reactor core analysis apparatus 20 may be formed of a single apparatus, an apparatus integrated with the covariance data creation apparatus 10, or a plurality of apparatuses combining an arithmetic apparatus, a data server or the like, and is not limited to a particular configuration, similarly to the covariance data creation apparatus 10.

[0033] The second storage unit 22 stores various computer programs such as a reactor core calculation code C2 used for calculating the reactor core characteristics, a macroscopic covariance adjustment program P2 used for adjusting the macroscopic cross sections as the input values for the core calculations, and a reactor core characteristic evaluation program P3 used for creating reactor core characteristic covariance data. The second storage unit 22 also stores data such as sensitivity data that is data regarding a change in the reactor core characteristics accompanying a change in the macroscopic cross sections, reactor core characteristic measurement data measured by a measurement apparatus for measuring the reactor core characteristics, an adjustment quantity for adjusting the macroscopic covariance, and the reactor core characteristic covariance data derived based on the reactor core characteristics.

[0034] A reactor core 5 as an analysis target will now be described with reference to FIGS. 3 and 4. FIG. 3 is an explanatory view schematically illustrating the reactor core as an analysis target. FIG. 4 is a cross-sectional view of a fuel assembly as an analysis target cut along a plane perpendicular to an axial direction. As illustrated in FIG. 3, the reactor core 5 as a target of reactor core design is contained in a nuclear reactor. The reactor core 5 is composed of a plurality of fuel assemblies 6. Note that fuel exchange is performed for each fuel assembly 6.

[0035] As illustrated in FIG. 4, nn The fuel assembly 6 is filled therein with a moderator (coolant) 33, and is configured so as to allow a plurality of control rods 34 and an in-core nuclear instrumentation 35 to be inserted thereinto. For each fuel rod 29, the fuel pellets 30 having a cylindrical shape are arranged in its axial direction, and its outside is covered with the cladding tube 31.

[0036] The fuel assembly 6 has a quadrangular cross-sectional shape, and is composed of, for example, 1717 cells 40. The control rods 34 are inserted into 24 cells 40 out of the 1717 cells 40, and the in-core nuclear instrumentation 35 into a cell 40 in the assembly center. The cell 40 into which the control rod 34 is inserted is called a control rod guide tube, and the cell 40 into which the in-core nuclear instrumentation 35 is inserted is called an instrumentation guide tube. Additionally, the fuel rods 29 are inserted into the other cells 40. When the fuel assembly 6 is used for a boiling water reactor (BWR), the outside of the fuel assembly 6 is covered with a channel box. Meanwhile, when the fuel assembly 6 is used for a pressurized water reactor (PWR), the outside of the fuel assembly 6 is uncovered. An inter-assembly gap 32 exists outside the channel box in the BWR, and outside the fuel assembly 6 in the PWR.

[0037] Next, the lattice calculation code C1 and the reactor core calculation code C2 used for the nuclear design calculation will be described. The lattice calculation code C1 is a calculation code used for the assembly calculation, and the reactor core calculation code C2 is a calculation code used for the core calculation.

[0038] The lattice calculation code C1 is used to perform various calculations such as resonance calculation, neutron transport calculation, burnup calculation and assembly (nuclear constant) calculation based on specification data regarding the fuel assembly 6 and the microscopic cross sections acquired from the cross section library stored in the first storage unit 12 of the covariance data creation apparatus 10 by using the microscopic cross sections as input values. Note that examples of the specification data include a radius of the fuel rod, an inter-assembly gap, a fuel composition, a fuel temperature, and a moderator temperature.

[0039] The lattice calculation code C1 is a code employing a quadrangular geometric shape, which is a cross section of the fuel assembly 6 cut along a plane perpendicular to the axial direction, as a two-dimensional analysis target area 50 (see FIG. 4), and enabling calculation of nuclear constants including the macroscopic cross sections in the analysis target area 50. Note that the nuclear constants are input values used for the reactor core calculation code C2, and examples of the nuclear constants include a diffusion coefficient, an absorption cross section, a removal cross section, and a formation cross section. That is, the macroscopic cross sections as the input values for the core calculations are generated by performing the assembly calculations using the lattice calculation code C1.

[0040] The reactor core calculation code C2 is used to perform the core calculations by setting the calculated nuclear constants to rectangular-parallelepiped small-volume fuel nodes (not illustrated) obtained by axially dividing the fuel assembly 6 into a plurality of segments. The fuel nodes represent the reactor core. The reactor core calculation code C2 is a code enabling evaluation of nuclear characteristics in the reactor core (the reactor core characteristics) such as a critical boron concentration, a power distribution, and a reactivity coefficient by performing the core calculations.

[0041] The covariance data creation apparatus 10 causes the first arithmetic unit 11 to execute the lattice calculation code C1 stored in the first storage unit 12 based on an input parameter inputted from the first input unit 13. The covariance data creation apparatus 10 thereby performs the assembly calculations by using the lattice calculation code C1 to calculate the macroscopic cross sections in the analysis target area 50 of the fuel assembly 6. Additionally, the reactor core analysis apparatus 20 causes the second arithmetic unit 21 to execute the reactor core calculation code C2 stored in the second storage unit 22 based on the calculated macroscopic cross sections. The reactor core analysis apparatus 20 thereby performs the core calculations by using the reactor core calculation code C2 to derive the reactor core characteristics of the reactor core 5. The reactor core analysis apparatus 20 performs macroscopic covariance adjustment and reactor core characteristic evaluation based on the derived reactor core characteristics. That is, the reactor core analysis apparatus 20 has a function of adjusting the macroscopic covariance and a function of evaluating the reactor core characteristics, and the second arithmetic unit 21 is an arithmetic unit capable of executing these functions. Note that the reactor core analysis apparatus 20 may be separated into an apparatus having the function of adjusting the macroscopic covariance and an apparatus having the function of evaluating the reactor core characteristics, and is not limited to a particular configuration.

[0042] Next, processing steps for generating the macroscopic covariance data by the covariance data creation apparatus 10 described above will be described with reference to FIG. 5. The covariance data creation apparatus 10 executes the covariance data creation program P1 to execute the processing steps for generating the unadjusted macroscopic covariance data.

[0043] In the covariance data creation apparatus 10, the first arithmetic unit 11 first acquires microscopic covariance data that is data regarding uncertainties of the microscopic cross sections in the cross section library stored in the first storage unit 12 (Step S11: Data acquisition step). The first arithmetic unit 11 then derives N sets of perturbation quantities of the microscopic cross sections by random sampling technique by using the microscopic covariance data. Deriving the perturbation quantities of the microscopic cross sections by the random sampling technique enables acquisition of thermal-hydraulics and burnup feedback effects noticeable in the reactor core of the light water reactor. The first arithmetic unit 11 generates microscopic perturbation data from the derived N sets of perturbation quantities of the microscopic cross sections (Step S12: Microscopic perturbation data generation step). The first arithmetic unit 11 stores the generated microscopic perturbation data in the first storage unit 12.

[0044] Subsequently, the first arithmetic unit 11 executes the assembly calculations based on the generated microscopic perturbation data, i.e., the respective microscopic cross sections having the first to Nth perturbation quantities to derive N sets of macroscopic cross sections individually corresponding to the first to Nth perturbation quantities (Step S13: Macroscopic cross section derivation step). As a calculation condition for executing the assembly calculations, a predetermined parameter as a representative is previously selected as a representative parameter from parameters regarding a reactor core state of the reactor core 5 including the fuel assemblies 6. At the macroscopic cross section derivation step S13, the assembly calculations based on the microscopic perturbation data are executed using the selected representative parameter as the calculation condition. Selecting the parameter can decrease the number of parameter combinations and reduce assembly calculation load. Note that a parameter highly dependent on the macroscopic covariance data to be generated is selected as the representative parameter. The first arithmetic unit 11 then generates the macroscopic covariance data that is data regarding uncertainties of the macroscopic cross sections based on the derived N sets of macroscopic cross sections (Step S14: Macroscopic covariance data generation step). The macroscopic covariance data is, for example, a standard deviation of the derived N sets of macroscopic cross sections. The first arithmetic unit 11 stores the generated macroscopic covariance data in the first storage unit 12.

[0045] Subsequently, the first arithmetic unit 11 derives N sets of perturbation quantities of the macroscopic cross sections by the random sampling technique by using the generated macroscopic covariance data. The first arithmetic unit 11 generates macroscopic perturbation data from the derived N sets of perturbation quantities of the microscopic cross sections (Step S15: Macroscopic perturbation data generation step). The first arithmetic unit 11 stores the generated macroscopic perturbation data in the first storage unit 12, and outputs the generated macroscopic perturbation data to the reactor core analysis apparatus 20.

[0046] As described above, the covariance data creation apparatus 10 executes the processing steps for generating the macroscopic covariance data to develop the uncertainties of the microscopic cross sections into the uncertainties of the macroscopic cross sections and generate the macroscopic covariance data regarding the uncertainties of the macroscopic cross sections. In generating the macroscopic covariance data alone, the step S15 may be omitted.

[0047] Next, processing steps for adjusting the macroscopic covariance by the reactor core analysis apparatus 20 described above will be described with reference to FIG. 6. The reactor core analysis apparatus 20 executes the macroscopic covariance adjustment program P2 to execute the processing steps for adjusting the macroscopic covariance. In the reactor core analysis apparatus 20, the macroscopic perturbation data outputted from the covariance data creation apparatus 10 is previously stored in the second storage unit 22.

[0048] In the reactor core analysis apparatus 20, the second arithmetic unit 21 first executes the core calculations based on the macroscopic perturbation data stored in the second storage unit 22, i.e., the respective macroscopic cross sections having the first to Nth perturbation quantities to derive N sets of reactor core characteristics individually corresponding to the first to Nth perturbation quantities (Step S21: Reactor core characteristic derivation step). The second arithmetic unit 21 then acquires sensitivity data, by deriving, as the sensitivity data, a relation between a change in the N sets of macroscopic cross sections and a change in the N sets of reactor core characteristics accompanying the change in the N sets of macroscopic cross sections based on the derived N reactor core characteristics (Step S22: Sensitivity data acquisition step). The sensitivity data may be stored in the second storage unit 22.

[0049] Subsequently, the second arithmetic unit 21 acquires reactor core characteristics measured by a measurement apparatus for measuring the reactor core characteristics of the reactor core as reactor core characteristic measurement data (Step S23: Measurement data acquisition step). The reactor core characteristic measurement data is data previously measured a few cycles before, and is stored in the second storage unit 22.

[0050] After acquiring the sensitivity data and the reactor core characteristic measurement data, the second arithmetic unit 21 derives an adjustment quantity for adjusting the macroscopic covariance from an equation (1) described below based on the acquired sensitivity data (Step S24: Adjustment quantity derivation step).

[00001]$\begin{array}{cc}.Math..Math.M_{\mathrm{ADJ}}={\left(\frac{1}{N}.Math..Math..Math.T.Math..Math..Math..Math.R^T\right)\left[\left(\frac{1}{N}.Math..Math..Math.R.Math..Math..Math..Math.R^T\right)+V_e+V_m\right]}^{-1}.Math.{\left(\frac{1}{N}.Math..Math..Math.T.Math..Math..Math..Math.R^T\right)}^T& \left(1\right)\end{array}$

[0051] Here, the equation (1) is defined as follows:

M.sub.adj: adjustment quantity of macroscopic covariance
T: perturbation quantity of macroscopic cross section (as the input value)
R: perturbation quantity of reactor core characteristic (as the output value) in accordance with the perturbation of the macroscopic cross section
V.sub.e: uncertainty of reactor core characteristic as a measured value
V.sub.m: uncertainty of reactor core characteristic as a calculated value due to the calculation method (m)

[0052] The second arithmetic unit 21 adjusts the unadjusted macroscopic covariance (M.sub.0) based on the adjustment quantity (M.sub.adj) calculated by the equation (1) and derives an adjusted macroscopic covariance M from an equation M=M.sub.0+M.sub.adj (Step S25: Adjusted macroscopic covariance derivation step). The second arithmetic unit 21 generates adjusted macroscopic perturbation data by the random sampling technique based on the adjusted macroscopic covariance (Step S26: Adjusted macroscopic perturbation data generation step). The reactor core analysis apparatus 20 executes the processing steps for adjusting the macroscopic covariance as described above. The second arithmetic unit 21 stores the generated adjusted macroscopic perturbation data in the second storage unit 22.

[0053] Next, processing steps for generating the reactor core characteristic covariance data by the reactor core analysis apparatus 20 described above will be described with reference to FIG. 7. The reactor core analysis apparatus 20 executes the reactor core characteristic evaluation program P3 to execute the processing steps for generating the reactor core characteristic covariance data.

[0054] In the reactor core analysis apparatus 20, the second arithmetic unit 21 first executes the core calculations based on the adjusted macroscopic perturbation data stored in the second storage unit 22, i.e., the respective macroscopic cross sections having the first to Nth perturbation quantities to derive N sets of reactor core characteristics individually corresponding to the first to Nth perturbation quantities (Step S31: Reactor core characteristic derivation step). The second arithmetic unit 21 then generates the reactor core characteristic covariance data that is data regarding uncertainties of the reactor core characteristics based on the derived N sets of reactor core characteristics (Step S32: Reactor core characteristic covariance data generation step). The reactor core characteristic covariance data is, for example, a standard deviation of the derived N reactor core characteristics. The second arithmetic unit 21 stores the generated reactor core characteristic covariance data in the second storage unit 22.

[0055] As described above, the reactor core analysis apparatus 20 executes the processing steps for generating the reactor core characteristic covariance data to develop the uncertainties of the macroscopic cross sections into the uncertainties of the reactor core characteristics and generate the reactor core characteristic covariance data regarding the uncertainties of the reactor core characteristics.

[0056] As described above, in accordance with the present embodiment, the covariance data creation apparatus 10 can generate the macroscopic covariance data. By using the generated macroscopic covariance data, the reactor core analysis apparatus 20 can perform the core calculations based on the macroscopic cross sections. Thus, the macroscopic covariance can be targeted for adjustment in evaluating the uncertainties of the reactor core characteristics. This allows the core calculations to be performed without performing the assembly calculations. Therefore, the assembly calculations can be omitted, which leads to prevention of an increase in calculation cost.

[0057] Additionally, in accordance with the present embodiment, the assembly calculations can be executed using the representative parameter as the calculation condition. Thus, the assembly calculations can be executed without using unnecessary parameters for generating the covariance data. This reduces calculation load.

[0058] Moreover, in accordance with the present embodiment, the adjusted macroscopic covariance can be derived by adjusting the macroscopic covariance. Here, the adjusted macroscopic covariance can be derived by performing the core calculations without performing the assembly calculations. Therefore, the assembly calculations can be omitted, which leads to prevention of an increase in calculation cost.

[0059] Furthermore, in accordance with the present embodiment, the reactor core characteristic covariance data can be generated by deriving the macroscopic cross sections using the adjusted macroscopic covariance data, and deriving the reactor core characteristics corresponding to the derived macroscopic cross sections. Here, the reactor core characteristic covariance data can be derived by performing the core calculations without performing the assembly calculations. Therefore, the assembly calculations can be omitted, which leads to prevention of an increase in calculation cost. Additionally, the uncertainties of the reactor core characteristics can be evaluated by using the reactor core characteristic covariance data.

REFERENCE SIGNS LIST

[0060] 5 REACTOR CORE

[0061] 6 FUEL ASSEMBLY

[0062] 10 COVARIANCE DATA CREATION APPARATUS

[0063] 11 FIRST ARITHMETIC UNIT

[0064] 12 FIRST STORAGE UNIT

[0065] 13 FIRST INPUT UNIT

[0066] 14 FIRST OUTPUT UNIT

[0067] 20 REACTOR COPE ANALYSIS APPARATUS

[0068] 21 SECOND ARITHMETIC UNIT

[0069] 22 SECOND STORAGE UNIT

[0070] 23 SECOND INPUT UNIT

[0071] 24 SECOND OUTPUT UNIT

[0072] 29 FUEL ROD

[0073] 30 FUEL PELLET

[0074] 31 CLADDING TUBE

[0075] 32 INTER-ASSEMBLY GAP

[0076] 33 MODERATOR

[0077] 34 CONTROL ROD

[0078] 35 IN-CORE NUCLEAR INSTRUMENTATION

[0079] 40 CELL

[0080] C1 LATTICE CALCULATION CODE

[0081] C2 REACTOR CORE CALCULATION CODE

[0082] P1 COVARIANCE DATA CREATION PROGRAM

[0083] P2 MACROSCOPIC COVARIANCE ADJUSTMENT PROGRAM

[0084] P3 REACTOR CORE CHARACTERISTIC EVALUATION PROGRAM