WO2001011633A2 - Method, computer programme and computer programme interface for determining a characteristic value of a nuclear reactor - Google Patents

Abstract

The invention concerns a method, a computer programme and a computer programme interface for determining a characteristic value of a nuclear reactor. It is necessary to resort to a plurality of input parameters (E), linked to one another in rather complex form, to determine and represent a characteristic value (K) of a nuclear reactor (1). The method, the computer programme (21) and the user interface (37) of the invention enable to avoid incoherence due to erroneous inputs. Said programme operates, in the form of an input/output filter, with inputs (E) whereof the quality is guaranteed, and determined characteristic values (K). Furthermore it uses an Internet environment (31, 33, 35).

Description

 description

Method, data processing program and surface of a data processing program for determining a parameter of a nuclear reactor

The invention relates to a method for the automatic quantitative determination and display of a parameter describing an operating state of a nuclear reactor, in particular also a nuclear reactor core and / or a fuel element operated in the nuclear reactor core. The invention further relates to a data processing program and a surface of a data processing program and a data processing system for carrying out the method. The data processing system comprises at least one input / output point and / or a computing stage and / or a database, for example stored in a database. In the method, an input required for a computing program is processed at a computing level in which various parameters can be determined quantitatively.

The monitoring of an operating state of a nuclear reactor, in particular the monitoring of the nuclear reactor core with the fuel elements contained therein during an operating cycle, is of the greatest interest for the effective and safe operation of a nuclear reactor. Monitoring takes place, for example, by means of an automatic control system as described in US Pat. No. 5,317,606. However, not every parameter of the operating status can be used at all times. For example, measurements of material properties of the nuclear reactor core, e.g. Corrosion status data, accessible only when the nuclear reactor is off by removing and examining fuel assemblies from the nuclear reactor core.

It is therefore common for important parameters that ultimately determine the effective function and safety of a reactor can be predetermined and monitored in certain time steps within an operating cycle using simulation calculations. The input and output values of such simulation calculations are calibrated on the basis of empirical and measured values, so that such calculations provide reliable and equivalent information about important nuclear reactor parameters for a measurement.

The relevant parameters include those that describe the neutron physics properties of the reactor core. For this purpose, at least the spatio-temporal solution of a three-dimensional neutron diffusion equation based on a corresponding model is necessary for the reactor core. The specification of thermohydraulic parameters also requires the spatio-temporal solution of three-dimensional differential and / or integral equations of thermodynamics and hydrodynamics. The determination of material properties of structural parts of the nuclear reactor core and parameters relating to the fuel also requires knowledge of a wide range of material parameters and corresponding models for describing changing material and fuel properties in different neutron physical and thermohydraulic environments. In particular, a realistic analysis or forecast of a reactor condition also requires the solution of coupled problems that take into account the interaction of neutron physical, thermo-hydraulic and material properties.

So far, solutions to the problems just mentioned have been determined by reactor programs, which generally have complex numerics. It is immediately apparent from the above explanations that such reactor programs a) require a correspondingly generously dimensioned hardware environment (UNIX computer), b) the numerical solution to the problems mentioned is time-consuming and therefore cost-intensive, ie the correction or Repetition of an invoice once executed is generally not acceptable, but at least involves a great deal of effort, c) the determination of the input parameters for such calculations is a not inconsiderable problem solely due to the amount of data involved, d) even slightly incorrect starting values, or in the worst case, contradicting or redundant start information or input parameters for solving the equations can lead to entirely false statements or to the program being terminated. This is due to the mathematical structure of the equations to be solved, which include non-linearities and thus instabilities. The equations may only provide stable and realistic solutions if a possibly very limited starting parameter range is specified.

The operation of such reactor programs requires, among other things, due to the reasons mentioned, generally a special knowledge that goes beyond the generally customary specialist knowledge and in some cases also an intimate knowledge of the theory of reactor physics and numerics. The operation of such reactor programs on locally installed UNIX computers by non-specialists therefore leads to considerable difficulties and due to the large number of possible options for input parameters.

In particular, the linking of physically not possible states if the input parameters are entered incorrectly leads to incorrect results. If these are recognized, the calculations have to be repeated or the input parameters have to be laboriously repaired. In the worst case scenario, the reactor states are incorrectly forecast and the nuclear reactor is therefore incorrectly planned for operation. If, on the other hand, a specialist is commissioned to operate the reactor programs, it usually takes a considerable amount of time to obtain information for the input parameters, since the input parameters have to be subjected to a quality check, for example. It is therefore an object of the invention to specify how a parameter describing an operating state of a nuclear reactor can be determined.

To solve the problem, a method for automatic, quantitative determination and display of a parameter describing an operating state of a nuclear reactor is assumed. A parameter of a current or future operating state can be determined. For this purpose, an input required for a computing program is processed at a computing level in which various parameters can be determined quantitatively. The parameter can in particular also describe a nuclear reactor core and / or a fuel element operated in the nuclear reactor core.

In the case of such a method, the invention provides that the following method steps are carried out as part of a controlled (for example a menu-controlled and / or command-controlled) data processing program:

First of all, at a first input / output point, a number of ascertainable parameters is selected, which parameter is to be determined, and then the data processing program automatically carries out the following steps:

1. At least one computing program is defined from a plurality of computing programs stored in the computing stage, which allow a plurality of parameters to be determined quantitatively from one input each. 2. The values of the input parameters required for the input of the defined computing program are called up, for example, via a data connection, in particular from the input / output point and / or from a stored data stock, for example from a data stock stored in a database. 3. From the values of the required input parameters, the input for the specified computing program is formed and sent to the specified computing program at the computing level. 4. At the arithmetic stage, the defined arithmetic program is executed and an output is generated, which is checked and from which the selected parameter is subsequently determined quantitatively. 5. The quantitatively determined parameter is passed to the first or a second input / output point, and then - after receiving at the first or the second input / output point - the parameter is displayed.

At the beginning of the process, the data processing program receives the decisive information with the selection of the parameter in order to automatically, i.e. to determine the characteristic size without the intervention of a specialist or another person.

The parameter to be determined can e.g. the core of the current temperature distribution. In particular, one or more of the parameters of a nuclear reactor can be determined quantitatively from the following addition:

- temperature coefficient and other moderator values e.g. Printing unit,

- boron effectiveness and / or concentration,

- control element effectiveness in normal and / or stucco rod configuration,

- Overskinetic characteristics, - Departure from Nucleate Boilmg ratios (DNB), e.g. also a void value, i.e. a proportion of steam in the coolant, or a loss of coolant accident analysis (LOCA)),

- neutron flux densities,

- fuel rod and / or fuel element output, - fuel rod and / or fuel element burn-up,

- Corrosion layer thickness on fuel rod sheaths (e.g. also a probability of a defect). The parameter can be determined as a single value and / or a list of values and / or as a function that is temporally and / or spatially dependent with a selectable step size. For example, a characteristic can be determined over several cycles or as a characteristic.

In the first process step, a suitable computer program and further necessary inputs are then determined in accordance with the selection of the parameter. For this purpose, a whole series of physical-technical relationships are taken into account by the data processing program, so that errors are avoided.

The necessary computer programs advantageously solve equations for describing neutron-physical and / or thermohydrauiical and / or coupled neutron ether-hydraulic processes in a nuclear reactor. This applies in particular to the solution of the problems mentioned in at least one dimension, advantageously in two or three spatial dimensions.

For example, the local temperature distribution depends on the temperature of the coolant fed in and the power distribution of the fuel elements. This power distribution is in turn determined by the activity distribution of the fuel and the neutron flow. The latter is influenced, among other things, by the position of the control stick and a boron concentration in the moderator. In contrast, it is practically independent of the corrosion status of the structural material. Correspondingly, in this case the data processing program can automatically generate each computing program for the activity distribution, for the neutron distribution, as a function of the control rod positions and boron concentration - and for the temperature distribution as a function of coolant temperature, activity distribution, control rod position and boron concentration to be selected.

The input parameters required for one or more computer programs in the second process step, for example the previous measured values of the coolant temperatures, the activity distribution of the fuel at the start of the reactor cycle and the previous movements of the control rod and other absorber materials (e.g. boron concentrations), are measured values e.g. available in a database. It is particularly advantageous to take into account one or more of the input parameters contained in the following addition in the context of the method according to the invention:

- position and / or position of a fuel element in the nuclear reactor core, - local position in the nuclear reactor core at which the parameter is to be determined quantitatively,

- load factor with which the nuclear reactor is operated,

Boron concentration and / or boron enrichment in the coolant of the nuclear reactor, position of the control rod in the nuclear reactor core,

- Burning state of the fuel elements and / or a neutron poison in the nuclear reactor core,

- Coolant and / or moderator properties in the nuclear reactor core.

The database mentioned can be created in particular at the input / output point. For this purpose, either a menu-driven selection in the data processing program at the input / output point can initiate a query of the database, or an input parameter can be entered via a keyboard at the input / output point. The stored data status can include in particular:

- neutron physical and / or

- thermohydraulic and / or - fuel-specific

- Structure-specific

Properties of a nuclear reactor, in particular Lists and / or schemes for:

- cross sections and / or

- temperature distributions and / or

- Burning conditions and / or

- loading conditions

- Material and / or substance distributions in the nuclear reactor core.

Material and substance distributions can affect, for example, boron enrichments in the coolant.

For example, in the third method step, the measured values of the coolant temperature from the data bank at the input / output point, the isotope composition and activity distribution from data from the fuel element supplier and a data connection are fed into the computer program.

The check of the output of the computer program provided in the fourth method step after its execution takes place on the one hand to ensure compliance with the calculation requirements and on the other hand to ensure compliance with the limit values by means of a comparison with empirical values. If the result is positive, quality-assured numerical values are available to describe the temperature distribution, for example.

This temperature at the individual locations of the reactor core can then be graphically represented in the fifth method step - for example on a screen in the reactor control center - and / or converted into a color code and / or stored in a data center as a temperature table.

In the case of the method, the invention is based on the knowledge that a menu-controlled implementation of the method with a data processing program contributes to avoiding errors, since on the one hand the user is offered only the options from a large number of possible options which are reasonable according to reactor engineering considerations , On the other hand mandatory entries are called by the user or automatically imported from a stored database. So as many input parameters as necessary and not more than necessary are read in.

After the selection of a parameter to be determined, the data processing process automatically determines at least a single or a sequence or a plurality of computer programs and all the input parameters required for this, and the values of the input parameters required for the input of the defined computer program are input on request or automatically called up. This has the advantage that, due to the technical considerations following the specifications of the data processing program, the amount of the necessary output parameters is complete but not overdetermined.

For example, in the case of a parameter for the determination of which a solution to a coupled problem of thermony orgy and neutron physics is necessary, it is not necessary to specify certain input parameters, since these have already been physically provided by the coupling of the two problems. On the other hand, part of the input parameters Dei of the solution of an isolated thermohydraulic or another part of the input parameters may be necessary for the solution of the neutron-physical problem. Contradictions and redundancies are avoided, for example, in the cases mentioned by this method according to the invention as part of a newly controlled data processing program.

It is also advantageous that when naming one or more points in time for which a parameter is to be determined, only the relevant point or points in time are retrieved from the input / output point and all input parameters assigned to a specified point in time from a stored database can be called up (for example from an existing reactor calculation or a reactor protocol or a core loading plan). The data status therefore advantageously no longer needs to be entered manually. This ensures the quality of the input parameters and guarantees their consistency. According to the invention, this can be done via a data connection, which can also lead, for example, to an "in situ" measurement system. For example, current measurement data could also be read in here. It is therefore advantageous with this type of input that the data processing program has an existing one Consistently reads complex data volumes while avoiding redundant inputs

User-defined input query is intelligently created by the data processing program.

Furthermore, it is advantageous that the data processing program automatically forms the input for the defined computing program from the values of the required input parameters. For example, an input parameter can, for example, be stored in a database, logged input form or e.g. can be entered for the standard unit of measurement, but nevertheless converted into a value that is favorable for the defined computer program and checked for its consistency or plausibility. In this way, quality-assured input is created for the specified computer program. Under certain circumstances, this input can be a large amount of data, so that it can be further advantageous to undertake data optimization, for example data compression and / or data identification, and / or encryption. The amount of data can thus be reduced and / or an advantageous transmission via a data connection can be accelerated and / or processing by the computing program can be accelerated. Further input processing can be created by the computer program.

Likewise, an automatic check of an output generated by the defined computing program, which is carried out by the data processing program, has the advantage that quality-assured statements can be made and complex billing Repetitions save both time and money. A check is carried out taking into account in particular the set input parameters, for example whether the generated output is suitable for determining the parameter. A comparison with empirical values can also be used to check whether the data of the output is in a physically and technically sensible plausibility range. The empirical values can, for example, be stored in a database.

Furthermore, the output can be filtered. Under certain circumstances, the selected parameter is already included in the output of the defined computer program and can be determined in a trivial manner from the output and passed to the first or the second input / output point. Under certain circumstances, the output also only includes the selected parameter in an implicit manner, so that it must first be determined quantitatively from the output data, for example by averaging or converting. In addition, the output can also include a much larger amount of data than is absolutely necessary for the quantitative determination of the parameter. The method according to the invention has the advantage that the data processing program takes on a type of filter function by means of which the output is checked and the selected parameter is selected, so that only the parameter previously selected for quantitative determination is passed to the first or a second input / output point becomes. This avoids the transmission of unnecessarily large amounts of data and has the advantage that, according to the method according to the invention, a user receives the determined value of the characteristic variable that he has selected and does not have to extract the value of the characteristic variable himself from the output data. The technical considerations required for this are implemented as part of the data processing program.

It is also an advantage of the method according to the invention that after receiving the parameter at the first or second th input / output point, the parameter can be displayed in different ways. Depending on the complexity of the parameter, this can be a simple number, a dependent function (for example of time or a local coordinate) in the form of a curve or a two-dimensional or three-dimensional visualized image of a data matrix.

The method according to the invention therefore has the advantage that, for example, when determining a relatively simply structured characteristic, a necessary complete reactor calculation is carried out, but due to the filtering effect of the method, a selected one for the input parameters or the input and the output values or the output quality-assured amount of data is swept down to what is necessary. On the other hand, even in the case of a complex structured parameter, a correspondingly detailed, quantified parameter can be returned and displayed in an advantageous manner.

According to an advantageous development of the method according to the invention, a comparison is made between the quantitatively determined characteristic variable on the one hand and a corresponding measured value or a data value from a stored data status on the other hand. This has the advantage that existing measured values can be checked for their plausibility or an existing data value can be updated, for example on a database. This favorably relates to a comparison with regard to an activation rate and / or a boron value and / or a corrosion value and / or a DNB ratio of a nuclear reactor. A DNB ratio indicates the distance from the "Departure from Nucleate Boiling", a measure of the critical overheating of a reactor.

On the basis of the comparison, it is also advantageous to determine a change in an existing operating state of a nuclear reactor and to bring about this under certain circumstances. This has the advantage that the user has a suggestion for one on the Future-oriented operational planning of the reactor is already obtained with the analysis of the existing operating state and does not have to be carried out explicitly and separately from the analysis of the existing operating state. This relates in particular to a change in the nuclear reactor core and / or in a fuel element contained in the nuclear reactor. For example, this can be a change in a power density distribution and / or a load factor for the nuclear reactor and / or a change in a spatial or temporal power peak. It may also be a change in the loading condition and / or a new loading plan. For example, reloading after a public reactor cycle may prove beneficial, or simply relocating a fuel element. In the latter case, it can be advantageous, for example, if a comparison result can be used directly to control a loading machine.

It is also advantageous if a change in an existing operating state of a nuclear reactor is registered in the stored database (e.g. on a data bank). An update of the stored data is carried out automatically and without errors.

According to a particularly advantageous development of the invention, at least the first input / output point and / or the computing level and / or the stored data inventory is networked, for example, in a database via an Internet environment that transmits to it. This can also include, for example, a "wide area network" (WAN) and / or a "local area network" (LAN). The development of the invention is based on the knowledge that the use of such an Internet environment for data transmission is possible through the selection of input filtering and output filtering by the data processing program, for example for data reduction and / or quality assurance. It is therefore a particular achievement of the invention, despite the complexity of the problems to be solved to solve the problems explained Calculations to have realized a sufficiently compact transmission of the input parameters or the input and the determined parameter or the output.

It is advantageous that, in particular, a plurality of input / output points are networked with a common computing level and / or a common stored database (e.g. on a database). The calculation programs can therefore be carried out on a correspondingly large and powerful calculation level. The input and output filters implemented by the method also enable effective work at the computing level, which can therefore also be used by a number of EmgaDe / output points.

It is advantageous to take one or more of the above-mentioned input parameters into account in the context of the method according to the invention. For this purpose, a stored database can in particular include one or more of the above-mentioned sizes. In particular, one or more of the above-mentioned parameters can be determined.

To achieve the object, the invention is also based on a data processing program on a data processing system for automatic, quantitative determination and display of a parameter describing an operating state of a nuclear reactor, the data processing system having at least one input / output point and / or a computing level and / or a stored one Data inventory, for example contained in a database, and an input required for a computing program is processed at a computing level in which various parameters can be determined quantitatively.

According to the invention, the data processing program comprises program modules linked to one another, with controlled output information of a first module acting as input information of a further module to avoid errors. The output information can arise, for example, as a result of a menu-controlled and / or command-controlled input. According to the invention, there is at least provision for: - The first module can be used at a first input / output point to select from a plurality of identifiable parameters which parameter is to be determined. According to the invention, the following essentially automatically implemented measures are implemented in the data processing program:

Via a second module, at least one computing program can be determined from a multitude of computing programs stored by the computing stage, which design a plurality of parameters to be determined quantitatively from one input each.

The third module can be used to call up the values of the input parameters required for the input of the computer program, in particular from the input / output point and / or from a stored database (e.g. a database stored in a database can be called up via a data connection).

Via the fourth module, the input for the computer program can be formed from the values of the required input parameters and, e.g. via a data connection, can be routed to the specified computing program at the computing level.

- Via a fifth module, the specified computing program can be executed at the computing level and an output can be generated in the process.

The output can be checked via a sixth module and the selected parameter can then be determined quantitatively.

Finally, the quantitatively determined parameter can be passed to the first or a second issuing / issuing point via a seventh module. According to the invention, the parameter can be quantitatively represented via an eighth module after receipt in the first or second input / output point. The advantages of such a data processing program according to the invention result in a corresponding manner from the advantages already explained of the method according to the invention for the automatic, quantitative determination and display of a parameter.

A data processing system is essentially understood to mean a plurality of computers and / or data processing machines which have at least one screen and / or a printer and / or another output medium, and have a keyboard and / or another output medium, as well as a storage medium for Data storage in the computer. An input / output point is understood in the narrower sense only as an input and output medium as just explained, in a broader sense also as a computer as just explained. A computing level is understood to mean, in particular, a generously dimensioned computer with an input / output point, the data memory and the computing capacity of the computing level being suitable for storing and numerically complex processing of large amounts of data. This can be, for example, at least one work station or a mainframe. An issue / issue point can be, for example, an ordinary personal computer.

According to a further development of the invention, a comparison between the quantitatively determined characteristic variable on the one hand and a corresponding measured value or a data value from a stored database, for example on a database (e.g. an empirical value) can be carried out on the other hand via a ninth module.

With this choice according to the invention, a change in an existing operating state of a nuclear reactor can advantageously be determined in a tenth module based on the comparison. Favorably, a change in an existing operating state of a nuclear reactor can be registered in the stored data store via an eleventh module.

Finally, it is expedient to enable at least one network of the first input / output point and / or the computing level and / or the data stored, for example, in a database via a twelfth module, in particular via an Internet environment which networks the mentioned points ( eg a wide area network and / or a local area network environment).

To solve the problem, a corer surface, in particular a user interface, of a data processing program on a data processing system for automatic quantitative determination and representation of a parameter which describes an operating state of a nuclear reactor is also assumed. The parameter also relates in particular to the operating state of a nuclear reactor core and / or a fuel element operated by a nuclear reactor core. Furthermore, the data processing system comprises at least one input / output point and / or a computing level and / or a stored database. It is also assumed that an input required for a computing program can be processed at a computing level in which various parameters can be determined quantitatively.

In the case of such a surface of a data processing program, the invention provides masks linked to one another, in order to avoid errors, a controlled (for example essentially menu-driven and / or command-controlled) input on one of the masks at an input / output point and / or Arithmetic stage calls another mask. Furthermore, according to the invention, one or more masks are part of the surface in the following payment: a first mask for selecting a characteristic variable to be determined from a plurality of characteristic variables that can be determined, a second mask for entering and / or selecting output parameters, a third mask for displaying the status of the computing program and / or for influencing the computing program, - a fourth mask for outputting and / or displaying the parameter.

The surface of a data processing program is advantageously designed in such a way that part of the masks, especially for a user at a first or a second input / output point, and another part of the masks, especially for a specialist who is responsible for the computing level, on an output / Issuing point accessible, which is assigned to the computing level. This can concern, for example, the third mask for displaying the status of the computing program and / or for influencing the computing program. The third mask can, however, also be used in a modified form to notify a user at an input / output point that the computer program has ended and the selected parameter has been determined.

According to the invention, the fourth mask not only permits a numerical representation of a selected characteristic variable, but in particular can also have a selected area for the pictorial representation of the characteristic variable in the form of a curve or, for example, a color-visualized two-dimensional or three-dimensional representation of a corresponding data matrix. It can also be advantageous to provide the mask with certain functions in the case of a pictorial representation, which allow the enlargement or reduction of certain image sections and / or the numerical representation of individual points of the image.

According to a further development of the surface of a data processing program according to the invention, the above-mentioned masks of the surface are essentially linked to several levels in accordance with a hierarchical structure. It is advantageous to provide a mask with a selection menu and / or an input field and / or an output table and / or an output area for displaying images or curves. This has the advantage that a user can be guided by general information on the details, and thereby offers a clear picture.

The invention also leads to a data processing system which comprises at least one input / output point, for example a terminal, and / or a computing level and / or a stored database (for example on a database). The individual components of the data processing system are designed such that one of claims 1 to 10 can be carried out on the inside of the method. In particular, a data processing program according to one of claims 11 to 16 is installed on such a data processing system. Conveniently, such a data processing program on said data processing system has a surface according to one of claims 17 to 19, which can be displayed on a screen of said data processing system

In order to solve the problem, an instruction for performing the above-mentioned method is also stored on a storage medium according to the invention. In particular, a data processing program according to a development of the invention described above and / or an instruction for executing a surface described above is stored on a storage medium. This applies in particular to the execution of the instructions and / or the data processing program and / or the surface with a data processing system.

According to the method according to the invention explained here, in particular in connection with the data processing program mentioned according to the invention and a corresponding surface of the data processing program, information necessary for solving the task is reliably and up-to-date. averaged and the input parameters required for a reactor program are called up completely but not in a specific manner. The result of a reactor calculation is then output in a quality-checked manner and, for example, an existing database is updated in accordance with a change made in order to possibly serve as the basis for further reactor calculations.

Advantageous embodiments of the invention are explained in more detail with the aid of a drawing. The figures show a schematic representation:

1 shows a previous data processing system for carrying out reactor calculations and determining a parameter, FIG 2 em data processing system for carrying out a

Method for automatic, quantitative determination of a parameter according to the invention, FIG. 3 shows a flowchart of the method for automatic, quantitative determination of a parameter, FIG. 4 shows a flowchart of a development of the method for automatic, quantitative determination of a parameter, FIG. 5 shows an example of an input mask of a surface a data processing program for the selection of a task area,

6 shows an example of the first mask for selecting a parameter to be determined from a plurality of determinable parameters, FIG. 7 shows an example of the second mask for entering and / or selecting input parameters,

8 shows an example of the fourth mask for outputting and / or displaying the parameter.

Identical elements have the same reference symbols in the figures. FIG. 1 shows a previous data processing system and method for determining a parameter describing an operating state of a nuclear reactor 1. The determination of the characteristic quantity K is carried out essentially on a powerful computer 3 (possibly a mainframe computer), which can access a data memory 5 and on which a reactor program 7 is executed to determine it. This can be, for example, a UNIX computer that is operated by a specialized service provider, as shown in FIG. 1. Under certain circumstances, it could also be operated at the site of a nuclear reactor 1.

In any case, the input parameters E necessary for carrying out the calculation for the reactor program 7 are usually not yet stored in a computer 3 on a powerful computer 3, but rather decentrally, in particular on local personal computers 9 e.g. at the location of a nuclear power plant 1 or elsewhere (e.g. at fuel element suppliers). The data material is usually very inhomogeneous. For example, data on identical sizes are available in different dimensions. The data are not selected, but must be selected from a variety of other information. As a rule, they are also not standardized to one or more reference sizes that made sense for a calculation.

The input parameters E must therefore be transferred to the database 5 of the computer 3 with considerable expenditure of time and essentially manually via an input station 11 of a powerful computer 3. In an advantageous case, the input parameters E are already available as a mobile data storage device 13 or a diskette 15. However, the input parameters are often only available in the form of a written document 17. In the latter case in particular, manual input must be made on the keyboard of the emitting station 11 on the computer 3. Not only is the cause of the error large due to simple input errors. Above all, there are also the considerable disadvantages already explained due to the redundancies and contradictions in the input that cannot be avoided by a normal user, in particular due to the variety of possible options when inputting the input parameters. In this case, consult a specialist. In the case of urgent calculations, this is often only possible via a telephone line 19. The correct input parameters are filtered out, a search for the cause of a fault, and the fault is remedied, as a rule by means of mutual frequent contacting of specialists by the user and vice versa via a telephone line. Finally, costly trips of one or more specialists to the location of a nuclear reactor 1 are sometimes necessary, where the above-mentioned problems must then be eliminated by means of personal measures by the specialist.

FIG. 2 shows the schematic representation of the method proposed here for the automatic, quantitative determination and representation of a parameter K describing an operating state of a nuclear reactor 1. In this case, a data processing program 21 is used to avoid the aforementioned errors in particular. It operates essentially menu-controlled or Controlled by the input of commands as coordinator and filter for the input of necessary input parameters E at an input / output point 23. This input / output point 23 and possibly a plurality of further input / output points 23 are generally located at the location of one individual reactor 1 and / or generally at further reactor locations 1.

According to the method proposed here, the input parameters E are transmitted via a data line 29 to suitable or several suitable computing programs 24 on a computing stage 25 for determining the characteristic variable K. It will Computer program 24 executed and monitored as part of data processing program 21.

The output of an individual or a plurality of computer programs 24 is checked, filtered and the parameter K is returned as a response via the data line 29.

Finally, the data processing program 21 serves to output and display a characteristic variable K on an input / output point 23.

After the selection of the parameter K, the data processing program 21 therefore primarily assumes the role of an intelligent input-output filter in the selection of the suitable computer programs 24, the input of input parameters E and the quality check of the determined parameter K. This affects, on the one hand, the Menu-driven selection of necessary input parameters E, which can be entered at an input / output point 23 or retrieved from a database 26, 27, 28. This can be, for example, a database 26 at a fuel element supplier or a data store 27 at a service provider or a data store 28 at a reactor site 1.

On the other hand, this concerns the quality check. Here, on the one hand, the task set is automatically recognized on the basis of the set parameters and, on the other hand, a determined one

Characteristic K checked for its consistency with the task and on the other hand for plausibility with already stored data values. This is done, for example, by an empirical value or a measured value M at a power plant location 1 or an empirical value on a database 26, 27, 28. The transmission of these values can take place from a power plant 1 or via a data line 30 or via the data line 29.

The data connection 29 can in particular also be an Internet connection, for example a wide area network (WAN) or also an e local area network (LAN). For this purpose, at least the data quantities M, E, K to be transmitted are compπ- P 1 1 1 PP Φ 1

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© + J TJ N d (fl 3 H x: d Φ φ rH x: QP x; P Φ d P 3 dd P gro 3 (fl H g N r ~ - υ 3 TJ Φ υ H υ O -H x: d Φ n P 4H QP Φ M g cö P TJ x: • ro PHPPPP cd • Φ to ro H υ HP d 44 Q, Φ PPP ro C φ (fl O TJ TJ Φ to H Φ HPH TJ to P Φ H Φ X5 3 (fl 3 P rH to H Φ P

H d XI TJ TJ 44 d d Φ d Φ Φ s g H M-4 P P Φ -. EH P (0 rH x: d 3 J P s TJ Cn υ H 3 d d 3 H Λ H Cn XI g P. H Φ> Ch Φ J 44 rH rH - N φ Φ O X

PH φ H ^• ^ r φ to υ Φ to PP m P Φ -5 d CNJ to nd • P φ φ P tu rH PP

^• «to CM P d (fl P cd P CNJ φ X) PH rH d 3 d φ PH φ g (0 3 Cn D, cQ C (fl Φ P --H Ή (fl M φ o P Φ Φ d ( fl H d> t α> Φ d Φ TJ rH to rö d 10 Q to φ 44 3 P φ H φ o Φ P XI Φ φ P ⁽ Ö P to P odoo Cn Π

TJ Φ Φ g H d P (fl H> M> P to PP d (fl Cn P Φ M t (fl HP 10> H s 4-1 d 1 g P g TJ φ Cn Φ rH d Φ 3 φ H TJ d to rH N φ Q φ φ Φ P 3

.. g Φ (fl d 5 H XI .V (fl φ d P φ TJ Φ 3 H 00 P d TJ X) TJ to cn to Φ P

+ J cö 4-> P 3 4-1 φ o υ 3 P φ t H rH P d P 3 Φ TJ d to d d φ H

P P H Cn 3 Φ 3 σ rj Cn d TJ P φ φ Φ H rH P d cG g d x; co Cn 3 o P - »φ φ Cn Φ O Φ (fl tu φ M Q Φ φ Cn P x: Φ φ Φ φ ro g 3 υ d d TJ H Φ X)

H O S P 4-1 d TJ oo rH x: TJ N M φ Φ rH H d CQ * P (fl 3 H 3 H P P c P

TJ P to 0. (fl Φ CTl H 44 CM o rH υ d P υ PP d Ci ⁽ 0 g P cn ro Φ P Φ cO H (fl

O &. φ P P P CNJ φ Ct, (fl (fl Φ 3 3 3 x: to Φ to P g 3 C d P H g g Φ P M J

MQO t (fl o φ TJ 44 P d P Φ PHPH (fl 3 d H φ PP 5 3 Φ o 4-> C g Cn TJ d rH d φ 3 gn co Φ X. Φ PH rH Φ g XI φ o Cn > to 4-1. ΛJ d P d P: s rH x: φ P TJ 03 N d Q XI ω XI Φ TJ P x: P> 44 d H d

4-> M 4-> (fl 3 o 3 H φ υ x: Φ P d 3 to P 4-1 P υ P (fl d H u φ

H (fl t Φ Cn M P s P P M υ d H d m Φ rH φ Cn CO 00 to 3 H H H P P H φ - P

Φ Φ H PS (fl H Φ to 3 Φ H s φ CNJ g PH d Φ ro H (fl g rH g Φ 3 Φ (fl öS P Φ Φ rH α, φ TJ Di φ dx: P s 3 P φ rH PP> IM X) P rH Q

Xl (0 P Cn rH φ XI PH d (fl H o P d cn rH (fl 3 Φ \ ^l φ l to d> PP φ OS gtx: dd P ä ω dgd

P υ Φ P H P H d (f Φ g φ H Cn 44 H to

P Φ H d Φ x: Φ CiΦ Cn P Φ 3 x; HP 3 ro 3 to d ⁽ 0 cfl P Φ to Q. d

Φ TJ rH H XI d to d to 3 rH 3 d P g Φ oo 4-1 d Q d to Φ Φ P (0 J 3 d t φ

TJ Cn Φ 3 ^ PPH Φ 3 D rH 'P ö (fl HX) CNJ to Φ Φ Φ φ> s Cn Q o <o HP d X) od P φ Φ TJ d Φ Cn φ P 3 3 cn Cn H x : HO s H Φ x;

(fl Φ g d Φ Φ P XI rH 3 d Cn ^ C /) H d »<c o g Q υ P g P g Φ P XJ

H Φ P dd to 4-J Φ P 3 d 1 Φ φ r- tn H co HD, φ ~ - P (fl to 44 τ) P <> to (fl P Cn 3 XI TJ V d υ φ φ XI P CNJ g 1 g HP to d (0 P g Cn P d P CNI HQ Φ d ro (fl d (fl x P 02 XI ⁽ 0 (fl φ d PH Cn HP Cn H d φ P d φ

3 Φ Φ P 1-1 3 Cn 3 υ 3 o (fl TJ Q .. to H Φ Φ o P (0 d Φ φ 3 o 3> 0

CQ tn s cq d φ P _^ dd Φ TJ P Cn <> φ Φ d X) gd H 3 P Φ 44 PC

+ J d (0 (fl H d .d P H cd Φ Da Cn to d P CNJ H ro (0 P 44 x: P d x: to

M 3 d TJ H 3 rH cd TJ ^ rd 3 d 3 TJ Cn P ιτ) d 3 10 H 3 cd to H 3 φ r υ Φ TJ o Φ Φ 4-ι rH P φ CN d rö (SJ P d P 00 H er Φ Φ (fl 44 Φ φ 44 TJ

(0 4-> d H X) (0 Φ P Φ P H Φ \ .V φ & 3 d Φ H X) P Cn X) to

D. PHP 4-> ⁽ 0 P 3 P Φ P 3 TJ g; φ • x: υ X) Cn «. QP d φ 3 ⁽ 0 3 in

P Φ X) ΛJ P Cn H <C to d Φ 44 g X) r- d υ ⁽ 0 Φ d P d (fl Φ> d Cn <

Φ H P d Φ to g φ H g Ö (fl Φ (fl 00 H H?: Cn Φ 3 Cn Φ • P rH φ d 4-J

> φ 3 H 3 6 Cn Φ πj. 1 d P P Cn φ Φ g d Q H x: ^ φ 3 to £ H g 3

H>, g Cn Φ P CNJ Φ Cn <P d Φ to α. , o H Φ Φ u> TJ Φ Cd Φ P

TJ 4-> 1 H d to Cn d (fl C3 O 3 H x: 10 Cn 1 Φ Cn N to Φ d o TJ Φ t 44

(O d: P Φ P TJ 3 φ dm α g Φ PP d υ P dd P g HG Φ g to to φ 3 fl 3 ⁽ 0 Φ H α d Cn H 3 Φ g H α α ro Cn Φ 3 φ to D 00 POP g Cn H rH H

VO <d TJ o 3 ⁽ 0 J Cn CTl XI (0 rH d Φ P .H Φ P Cn d Φ 1 (fl P co (fl d φ (fl TJ \ p XPP 3 ro (0 P x: Φ Cn φ • 1-4 rH ⁽ 0 3 P x: PP g Cn QP 3 ≥ P

_* - »! p υ Φ XI TJ 1 P x: 44 n cn υ X, TJ P Φ Q> P Φ υ Φ 3 or Cn P rH tx: P

O Φ to 4J υ dd M υ PM do to υ TJ Φ Cn PP rH d Cn P ddox! H rH υ (fl o HH d 3 Φ H Φ to Φ 3 HP d Φ dd X) X! Φ Φ d φ (fl H 3 φ HP 3 Φ 3 ro P g 4-> ⁽ Ö x: cd XI 2> P Cd D. ro PS 3 ⁽ 0 o (fl d>? P (fl X, φ UP TJ 2 tΛ mo LO o LΠ O LO rH rH CNJ ro ro

nes user of the data processing program 21. The Internet environment 33 of the user (eg intranet) is connected to an Internet environment 35 of the service provider (intranet) or a supplier within the framework of a higher-level internet environment 31 (eg extranet) via data lines 29, 30 ,

In a first method step VI, on a surface 37 m of a selection mask (which appears, for example, on an Internet site), for example by an input in the keyboard 39 at the input / output point 23, a characteristic variable K to be determined is selected from a selection of determinable characteristic quantities K selected. In the next method step V2, one or more assigned computer programs 24 are defined in accordance with the selection made. For this purpose, the method, in particular in the context of the data processing program 21, defines a list of input parameters E necessary for the quantitative determination of the parameter K. Above all, this list is consistent in itself and avoids redundancies and contradictions or the linking of physically not possible states for the input parameters E.

In a further method step V3, the input parameters E are again entered in a further input mask 39, for example using the keyboard 39 of an input / output point 23. The input parameters E called up in this way are already used in the above-mentioned method by the data processing program 21 checked for consistency and, if necessary, supplemented by data values from a stored data stock 41A, 41B, 41C, for example on a database 26, 27, 28, converted or offset to new input parameters. For this purpose, a database 28 with a database 28 at the location of the power plant 1 can either be accessed via a data line 30. Or via a data line 29, for example in the context of the Internet environment 31, to an external database 26 or 27, for example at a supplier or service provider be resorted to. At this point there is therefore communication via the Internet 31 between the Internet application 33 of the user and the Internet application 35 of the service provider.

If the set of input parameters E is complete and found to be error-free, then in the next method step V4, again within the data processing program 21, the input parameters E are adapted to a form of input necessary for the computer program 24. This can be, for example, standardization of input parameters E to an order of magnitude favorable for the computing program 24. For example, several input parameters E can also be combined to form a data field or data vector. The data record can also be compressed and encrypted or identified with regard to transmission via a data line 29. The data packet is then transmitted from the user's Internet environment 33 to the service provider's Internet environment 35.

There (FIG. 3B), the data is then determined in the next method step V5 by means of the selected computer program 24, and an output is generated in this way, which is subjected to a consistency check in a further method step V6. The data is usually determined on a correspondingly dimensioned computing stage 25 with a sufficient data memory 27 and computing capacity for carrying out the reactor programs 24. In the case of a consistency check, for example, the parameters that were set were used to identify which task had to be done and whether the output was to be done this task is sufficient. Furthermore, a check can be carried out with regard to the comparison of the characteristic variable K with empirical values (e.g. on a database 27) or measured values M (for example from a reactor core 2 or a database 28).

The generated output can include complicated data matrices that, for example, a temporal-spatial neutron Φ d 1 1 00

00 1 1 H Φ o 1> P n M 1 f φ HQ TJ Q d ⁽ Ö P Cn 1 cn 1 d 1 do Φ r-

© Cn φ P Φ S φ d 1 rH P rH d 3 P (fl to φ Φ d P 3 cö H P o d X) H XJ d H o Cn g d 3 Φ d TJ H d H 4-4 Φ Φ g d Φ Φ

0- to P Φ d (Ö υ P rH τj υ P P: - Cn P Φ P 3

63 3 o TJ P υ 4H rö rH H 44 to x: φ g φ P d rH

H rö CM PM to P do X) 3 Φ υ P o ro cö x: υ Φ υ H Φ x: to cö Cn to ö> Φ 1 PQP ro e- Φ d 3: 3 d> d P 3 rH td TJ P φ Φ 3 rH rl P od Φ r <ro l TJ ä d 3 Φ TJ P 4-1 rH 4> TJ P (0 (f Φ TJ ld Φ φ P φ d rH φ P (fl. Φ d PP rH d P> TJ H Φ

XJ o rH Cn M Q H φ to 3 x; H 3 Φ H- TJ

(fl H φ to Φ brf 3 TJ φ Cn ⁽ Ö XJ Di P x: do

H P P 3 rH. d d H 4-) P rö d u H to

ΛJ (0 cö φ d Φ P Φ H CM P φ P hH H φ

P d Φ Φ φ x: Φ Φ P P Φ g TJ Q

Ö 3 Ö> CQ d TJ o TJ Φ d> H P P rH φ

TJ Cu P 00 Φ PP o Cn g H Φ Φ 3 Cn d CQ P o ⁽ Ö CNJ P Φ Cn PP gs JNPH rH P φ TJ Φ 3 d P Φ o to Φ o Φ Φ ^■ "3 * Φ

Φ n P TJ d φ P Cu (fl TJ P 00> 3

P H P d d P Φ TJ H TJ Φ φ 00 P d to Cn P φ rö P W d Φ d x: d d d H Φ

H d φ g φ φ 3 H d υ H H Cn H g rH P

1-1 (fl s 3 g x: P φ rö tÖ Φ Φ d Φ «rr ro x: d M Φ υ Φ XJ P 10 d 3 Φ Q

Φ X) φ O d H TJ Φ d x: rH to XI TJ to TJ r- d rö rH Q H Φ TJ d Φ υ d Φ P Φ P H d d

CNJ H x; Φ 0- Cn d H P H Φ H φ σ> H Φ (fl Φ

Φ φ (fl d to d Φ Φ x: co x: a N g 3 3 P x: d ts! HP φ 3 c (0 υ t P 3 to to υ to H Φ Φ Cn rH Φ rH 44 t HH 3 PP rH φ H rH φ d TJ XJ rH H φ P Φ rH Φ d φ P Φ XI rH

(fl H (0 o (fl Φ rH H Φ x: P CQ Φ d o H d TJ to φ rH P x: Ci> υ d CQ P Q Ciφ d

P rH (fl M P to υ to rH Φ g φ to P H

Φ (fl to d Φ P tO H d Φ (0 Φ (0 P • H (fl 44 J rH x: ⁽ Ö N (fl d Φ Φ 3 Φ to Φ dt Φ Q Φ ox: (fl υ XJ P α rα CQ d 3 Φ TJ rH P XJ XI υ 3 d 3 Φ .. H φ dd 3 P rö Φ d TJ td XI P g TJ x: PPX Φ t

Φ CÖ 3 P φ d P H Φ rH H υ φ to P P

TJ d d co OQ 3 Φ Φ H rH x: to d H φ cn

PP d QNP φ d υ d H Φ cα Φ φ Φ P rö g Cn PP x: P Φ ⁽ Ö 3 Φ rH o rH t

5 TJ Φ .y P H d 3 to υ to P 2 s to P P P o TJ Φ Φ 3 d H to Φ x: 10 i φ

P o X d X! rH Φ Φ Cn ro • 44 tdd P r rH d HPQ "XI P 4H P 3 3 φ dd rH Φ φ Φ Φ oo P rö P c (fl rö H Φ H 1 φ TJ> α CNJ H 10 PP TJ Φ Φ Q! -S x; from PPP odg Φ 3 Φ> H CD «

(0 Φ 3 P H P P TJ Cn H to rH> t d r-

- ~ φ 3 «n d Cd H x: g Φ x; Φ Φ Φ CNl o Cn d P φ Φ m g P υ x: c TJ P

O P d P d φ g P xi d to (fl P to υ o rH

(fl Φ φ φ TJ 3 3 ro Φ d P φ d ⁽ 0 P in Φ <>

TJ X) d ^ o AJ N Cn TJ HJ Cn TJ d Di 00 P CNJ T

with a measurement value M retrieved from a reactor 1, a reactor core 2, or a fuel element 4. If the comparison V yields a change in the ascertained characteristic variable K in comparison to the measured value M or the data value D, then change information I can possibly be returned to the user's Internet environment via a data line 43 and there to an input / output -Position 23 are shown or stored in a database 28 of the user. If the user accepts this change I, for example via a data connection 43A, the stored database 41B can be updated on the database 27 at the service provider (possibly also in the database 41A on the database 26 at the supplier). The stored database 41C on the database 28 can also be updated synchronously by the user.

It is also possible to cause a change in the corresponding characteristic variable K in the reactor 1 via a data connection 43B - for example the change in a load factor in the reactor core 2 or the change in a loading plan for a fuel assembly 4. The analysis of an existing operating state of a nuclear reactor 1 , in particular the determination of a characteristic variable K of a nuclear reactor 1, can therefore cause a necessary change I of the operating state via a data link 43B in the reactor 1 and at the same time (synchronously) update the currently documented operating state on a database 26, 27 via a data line 43A. The analysis of the current operating state via the determination of a characteristic variable K of a reactor 1 can therefore directly intervene in the future-oriented operating planning of a nuclear reactor 1.

FIG. 5 shows an example of a mask 37A for a surface 37 of a data processing program 21. This can appear at the start of the data processing program 21 on a website that is called up, for example, at an input / output point 23 of a data processing system. On According to this example, field 53 identifies the purpose of the mask 37A - namely the automatic, quantitative determination and display of a characteristic quantity K describing an operating state of a nuclear reactor 1 by means of "reactor calculations". The mask 37A provides the option by means of a selection menu 61 by means of a pointer 62 (for example A service can be selected using a computer mouse), for example analysis 61A of reactor properties (determination of characteristic size) or comparison 61B of a determined characteristic value K with a measured value M that can be called up from a power plant or a data value D stored in a database The analysis 61C of fuel-specific properties can also be carried out or a search 61D can be carried out on a stored database 4 LA, 41B, 41C on a database 26, 27, 28. Via a field 55, a determined parameter K can be called up by a computing stage 25 and information about field 57 (e.g. Ko comments) to the service provider. An alphabetical list of all possibilities within the surface 37 can be selected via field 59. In addition, a language of the upper sheet 37 can be selected according to the user via the field 51. By actuating a field 63 with the pointer 62, a message can be sent to a specialist responsible for the reactor program 24 or via a field 65 to the service provider.

If, for example, the selection 61A is made in the first mask 37A, in the present example of a surface 37, a further first mask 37B (FIG. 6) is called up, which selects a characteristic variable K to be determined from a plurality of characteristic variables K which can be determined allowed. This can be a selection 67 of neutron physical parameters K, for example.

According to the present exemplary embodiment, one or more of the following parameters can be selected:

Isothermal or combined temperature coefficient, fuel temperature coefficient, Borwirksamkeit,

- zero-load boron concentrations (e.g. between 0-2000ppm), control effectiveness, control effectiveness of stucco rod configurations (e.g. affects limited control by jammed control rod),

Calculation of the effective Uberkπtikalitat. The remaining reference numerals correspond to those in FIG. 5.

The determination can be made as a function of time steps of different sizes.

For example, when selecting the parameter "fuel temperature coefficient" with the pointer 62, the following calculation is carried out, which the data processing program 21 carries out automatically:

The reactivity of the reactor is determined for reactor states in which

- the fuel temperature is varied by +/- 50K by a nominal value, and - the coolant temperature is kept constant.

The result (in this case several values for different fuel temperatures) is balanced by the data processing program 21 as a “fuel temperature coefficient” in a reactivity change (in the unit 10 ^“5 / K) and then checked for plausibility on the basis of experience and limit values. If the value lies within certain limits, the result is classified as "permissible" and is thus output to the user. Measures which lead to a variation in the fuel temperature within the limits queried can then be carried out by the user during reactor operation.

When selecting the task 61B with the pointer 62 (FIG. 5), there is the choice according to the present exemplary embodiment (analogous to FIG. 6):

Comparison of activation data, comparison of boron values, Comparison of corrosion values,

- Comparison of measured values from a database

In the task selection 61C with the pointer 62 (FIG. 5), according to the present exemplary embodiment (analogous to FIG. 6), the choice includes:

- Fuel element with a minimum DNB ratio, DNB ratio of a certain fuel element, spatial representation of fuel rod output in the core diagram, - spatial representation of fuel rod burn-offs in the core diagram (affects fuel and neutron poison, e.g. gadolinium burn-off), spatial fuel rod-based display of corrosion layer thicknesses in the core, - spatial Representation of fuel rod by layer of corrosion for a fuel element,

Calculation of the extent of damage in the LOCA case (Loss of Coalant Accident, fictitious),

- fuel history, fuel history of all rods. If a database 27 is selected, core schemes can be provided, for example, or a pool assignment or a list of fuel elements in the reactor pool or a list of fuel elements to be replaced or exchanged.

In the task selection 61D with the pointer (FIG. 5), according to the present exemplary embodiment (analogous to FIG. 6) there is a choice among other things: core schemes - pelvic occupancy

Fuel element lists

FIG. 7 shows an exemplary embodiment of a second mask 37C of a surface 37 of a data processing program 21 on a data processing system. The execution of the mask 37C depends on the parameter K selected for the determination in the first masks 37A, 37B and is determined by the data processing Program 21 determines. In this exemplary embodiment, the input of required input parameters E for a computer program 24 (reactor program) is called up via a table 69. A series of preset standard values E for the selection of a point in time T in the past or in the future for the calculation of a characteristic variable K can be selected and / or read in by actuating a field 74 with the pointer 62.

The input parameters concern:

- the time in the reactor cycle (TS, TP) the control rod position (CRC) the load factor (LOAD)

- DNB ratio (DNB) - fuel element position with associated DNB (DNBPOS) the local positions in the reactor pressure vessel (WXYZ)

- the burning of fuel and neutron poison (CB, BURC)

- the moderator density, (MODRHO)

- different moderator temperatures (MODTEMP, TINLET, TRISE) different moderator prints (MODP)

- additional, other data files (MTS, NO50)

Only a few fields 70 of table 69 can be filled in via keyboard 39 at an input / output point 23. The majority of the fields 72 in table 69 are filled, for example, by input parameters E, which are retrieved from a stored database 4 LA, 41B 41C in a database 26, 27 28. In some cases, the input parameters E in the fields 70 entered via an input / output point 23 are checked for consistency with the input parameters E in the fields 72 read from a database 26, 27, 28 or are calculated with these to form a new combined parameter , The measures necessary for this are carried out automatically by the data processing program 21. After confirmation of the entries in a confirmation field 75, the input parameters E of the table 69 are used by the data processing program 21 to generate an input for a computing program 24 which is suitable for determining the selected characteristic variable K.

FIG. 8 shows an exemplary embodiment of a third mask 37D of a surface 37 of a data processing program 21 for outputting and / or displaying a characteristic variable K. For this purpose, the right part of the mask in FIG

Characteristic K here for example quantitatively represent the spatial distribution of a neutron flux density in a reactor 2 by color gradations. By selecting a point P in this image 71 with the pointer 62, for example, an associated numerical value W of this point P can be represented in a left part of the mask of a numerical field 73.

Claims

claims

1. A method for the automatic, quantitative determination and display of a parameter (K) describing an operating state of a nuclear reactor (1), in particular also one

Nuclear reactor core (2) and / or a fuel element (4) operated in the nuclear reactor core (2), wherein input required for a computing program (24) is processed on a computing level (25) in which different parameters (K) can be determined quantitatively , characterized in that in the frame of a controlled (for example partially menu-controlled and / or controlled via a command) data processing program (21) to avoid errors - selected from a plurality of determinable parameters (K) at a first input / output point (23) which parameter (K) is to be determined, that the data processing program (21) automatically:

at least one computing program (24) is determined from a plurality of computing programs (24) stored by the computing stage (25), which allow a plurality of parameters (K) to be determined quantitatively from one input each,

- The values of the input parameters (E) required for the input of the defined arithmetic program (24) are called up, in particular from the input / output point (23) and / or from a stored database (41A, 41B, 41C), in particular on a database (26, 27, 28), e.g. Via a data connection (29), - the input for the specified computing program (24) is formed from the values of the required input parameters (E) and is passed to the specified computing program (24) on the computing stage (25), e.g. via a data connection (29),

- On the computing stage (25), the defined computing program (24) is executed and an output is generated, which is checked and from which the selected parameter (K) is then determined quantitatively, - The quantitatively determined characteristic (K) is passed to the first or a second issuing / issuing point (23), and that after a reception at the first or the second issuing / issuing point (23) the characteristic (K) is shown becomes.

2. The method according to claim 1, characterized in that em comparison (V) between the quantitatively determined parameter (K) on the one hand and a corresponding measured value (M) or a data value (D) from a stored data set (41A, 41B, 41C), for example on a database (26, 27, 28), on the other hand, in particular by comparing an activation rate and / or a boron value and / or a corrosion value of a nuclear reactor (1).

3. The method according to claim 2, characterized in that based on the comparison (V) a change in an existing operating state of a nuclear reactor (1) is determined, in particular a change in the nuclear reactor core (2) and / or contained in one in the nuclear reactor (1) Fuel element (4), e.g. a change in a power density distribution and / or in the loading condition and / or a new loading plan.

4. The method according to any one of the preceding claims, that a change in an existing operating state of a nuclear reactor (1) is registered in the stored database (LA, 41B, 41C), for example on a database (26, 27, 28).

5. The method according to any one of the preceding claims, characterized in that at least the first input / output point (23) and / or the computing stage (25) and / or the stored data stock (41A, 41B, 41C), for example on a database (26, 2, 28), is networked via an Internet environment (31, 33, 35), in particular via a WAN and / or LAN environment.

6. The method according to any one of the preceding claims, characterized in that a plurality of input / output points (23) with a common computing stage (25) and / or a common stored database (41A, 41B, 41C), for example on a data bank (26, 27, 28), are networked.

7. The method according to any one of the preceding claims, that the data stored (4 LA, 41B, 41C), for example on a database (26, 27, 28), comprises:

- neutron physical and / or

- thermohydraulic and / or

- fuel specific

- Structural material-specific properties of a nuclear reactor (1), in particular lists and / or schemes for:

- cross sections and / or

- temperature distributions and / or

- Burning conditions and / or - Loading conditions

- Material and / or substance distributions in the nuclear reactor core (2).

8. The method according to any one of the preceding claims, d a d u r c h g e k e n n z e i c h n e t that one or more of the required input parameters is included in the following payment:

- period of use and / or position of a fuel element (4) in the nuclear reactor core (2), - local position in the nuclear reactor core at which the parameter is to be determined quantitatively,

- load factor with which the nuclear reactor (1) is operated, Boron concentration and / or boron enrichment in the coolant of the nuclear reactor (1),

- position of the control rod in the nuclear reactor core (2),

- Burning state of the fuel elements (4) and / or a neutron poison in the nuclear reactor core (2),

- Coolant and / or moderator properties in the nuclear reactor core (2).

9. The method according to any one of the preceding claims, d a d u r c h g e k e n n z e i c h n e t that one or more of the parameters (K) of a nuclear reactor (1) are determined quantitatively from the following list:

- temperature coefficient,

- Boron effectiveness and / or concentration, - Control element effectiveness in normal and / or stucco rod configuration,

- supercritical factual,

- DNB behavior,

- neutron flux densities, - fuel rod and / or fuel element performance,

- fuel rod and / or fuel element burnup,

- corrosion scr. chtαicke in the nuclear reactor core (2) and / or in the fuel assembly (4), the parameter as an individual value and / or a list of values and / or as one with a selectable

Step size temporally and / or spatially dependent function is determined.

10. The method according to any one of the preceding claims, d a d u r c h g e k e n n z e i c h n e t that the required computer programs (24) equations for the temporal and spatial description of neutron physics and / or thermohydraulic and / or coupled neutron thermohydraulic processes in a nuclear reactor (1) loose.

11. Data processing program (21) on a data processing system for automatic quantitative determination and Representation of an operating state of a nuclear reactor

(1) Descriptive parameter (K), in particular also a nuclear reactor core (2) and / or one in the nuclear reactor core

(2) operated fuel element (4), the data processing system comprising at least one input / output point (23) and / or a computing stage (25) and / or a stored database (41A, 41B, 41C), in particular on a database (26 , 27, 28), and an input required for an arithmetic program (24) is processed on an arithmetic stage (25) in which various parameters (K) can be determined quantitatively, characterized by interlinked program modules, one to avoid errors controlled ⁽ for example partially menu-controlled and / or controlled via a command) output information of a first module acts as input information of another module, and at least:

- The first module at a first input / output point (23) can be used to select from a plurality of identifiable parameters (K), which parameter (K) is to be determined, and automatically:

at least one computing program (24) can be determined via a second module from a plurality of computing programs (24) stored in the computing stage (25), which allow a plurality of parameters (K) to be determined quantitatively from one input each,

- Via a third module, the values of the input parameters (E) required for the input of the computing program (24) can be called up, in particular from the input / output point (23) and / or from a stored database (41A,

41B, 41C), in particular on a database (26, 27, 28), e.g. via a data connection (29, 30),

the input for the computing program (24) is formed via the fourth module from the values of the required input parameters (E) and, for example via a data connection (29), can be conducted to the defined computing program (24) on the computing level (25), - Via a fifth module, the defined computing program (24) can be executed at the computing level (25) and thereby em output can be generated

- Can be checked via a sixth module and from which the selected parameter (K) can then be determined quantitatively,

- The quantitatively determined parameter (K) can be passed to the first or a second issuing / issuing point (23) via a seventh module, and via an eighth module after receipt in the first or second issuing / issuing point (23) the parameter (K) can be represented quantitatively.

12. The data processing program (21) as claimed in claim 11, which also means that a comparison (V) between the quantitatively determined characteristic variable on the one hand and a corresponding measured value or a data value from a stored database (41A, 41B, 41C) on the other hand can be carried out via a ninth module.

13. Data processing program (21) according to claim 12, so that a tenth module can determine a change in an existing operating state of a nuclear reactor (1) based on the comparison (V).

14. Data processing program (21) according to one of claims 11 to 13, d a d u r c h g e k e n e z e i c h n e t that a change in an existing operating state of a nuclear reactor (1) in the stored database (41A, 41B, 41C) can be registered via an eleventh module.

15. Data processing program (21) according to one of claims 11 to 14, characterized in that via the twelfth module at least the first input / output point (23) and / or the computing stage (25) and / or the stored data stock (41A , 41B, 41C) about one there transmitting Internet environment can be networked, in particular via a WAN and / or LAN environment.

16. Surface (37) of a data processing program (21) on a data processing system for the automatic quantitative determination and display of a parameter (K) describing an operating state of a nuclear reactor (1), in particular also a nuclear reactor core (2) and / or one in the nuclear reactor core (2) operated fuel element (4), the data processing system (21) containing at least one input / output point (23) and / or a computing stage (25) and / or a stored database (41A, 41B, 41C) and one for a computing program ( 24) the required input is processed on a computing level (25), n which different characteristic quantities can be determined quantitatively, characterized by interlinked masks (37A, 37B, 38, 40), an essentially controlled (eg menu-controlled and / or command-controlled) input on one of the masks (37A, 37B, 37C, 37D) at an input / output location (2nd 3) and / or a computing stage (25), calls up a further mask (37A, 37B, 37C, 37D), and one or more masks (37A, 37B, 37C, 37D) are included in the following payment:

- a first mask (37A, 37B) for selecting a characteristic variable (K) to be determined from a plurality of determinable characteristic variables (K)

a second mask (37C) for input and / or selection of input parameters (E),

a third mask for displaying the status of the computing program (24) and / or for influencing the computing program (24),

- A fourth mask (37D) for outputting and / or displaying the parameter (K).

17. The surface (37) of a data processing program (21) according to claim 16, so that the masks (37A, 37B, 37C, 37D) are linked to several levels essentially according to a hierarchical structure.

18. Surface (37) of a data processing program according to claim 16 or 17, characterized in that a mask (37A, 37B, 37C, 37D) em selection menu (61,67) and / or em input field (69) and / or an output table (69) and / or an output surface (71) for displaying images or curves.

19. Data processing system comprising at least one input / output point (23) and / or a computing stage (25) and / or a stored database (4 LA, 41B, 41C), for example on a database (26, 27, 28 ), characterized in that it can be used to execute a method according to one of Claims 1 to 10, and / or it can be used to execute a data processing program (21) according to one of Claims 11 to 15, and / or an upper flap (37) according to one of the Claims 16 to 18 is operable.

20. Storage medium on which a data processing program for carrying out the method according to one of claims 1 to 10 is stored, in particular a data processing program (21) according to one of claims 11 to 15 and / or a data processing program for executing a surface (37) according to one of claims 16 to 18, in particular with a data processing system.