CN112819323B - Calculation method and system for nuclear power station spent fuel transportation plan formulation - Google Patents
Calculation method and system for nuclear power station spent fuel transportation plan formulation Download PDFInfo
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Abstract
The method comprises the steps of obtaining the outward transportation quantity and the outward transportation total quantity of each type of component according to the detailed information of the component and the basic information of a receiving facility; calculating the receivable amount of each type of component according to the basic information of the receiving facility; determining the actual total transportation amount of each type of component transported to each receiving facility according to the total outward transportation amount and the receivable amount, and calculating the actual outward transportation amount and the actual receiving amount; and calculating the outward movement component of each type of component according to the actual outward movement quantity and the actual receiving quantity. The method has the advantages of improving the accuracy and planning efficiency of spent fuel transportation planning and achieving the effect of comprehensively planning spent fuel transportation of a plurality of nuclear power stations.
Description
Technical Field
The application relates to the field of spent fuel transportation technology, in particular to a calculation method and a system for making a spent fuel transportation plan of a nuclear power station.
Background
Spent nuclear fuel, also known as irradiated nuclear fuel, is spent nuclear fuel that has been subjected to irradiation, and because its uranium content is insufficient to continue to support the reaction, it needs to be transported out of the reactor, and spent fuel transported out of the reactor must be transported to a spent fuel reprocessing plant or elsewhere for spent fuel reprocessing. The spent fuel transportation must adopt special containers and special transportation tools, and other processes such as audit management are needed, so a detailed transportation plan needs to be made to guide the transportation work before the spent fuel transportation is carried out.
Only a certain nuclear power station demand is considered in the original formulation of a spent fuel transportation plan, along with the continuous operation of the nuclear power station and the gradual increase of the construction quantity of the nuclear power station, the current spent fuel transportation demand is continuously increased, the urgent degree of spent fuel transportation of each nuclear power station needs to be considered in a lump, and the receiving capacity and the container resource of the receiving facility are adjusted to ensure the safe and stable operation of each nuclear power station and the receiving facility.
In the current planning of spent fuel transportation amount, the informatization degree of a spent fuel transportation amount calculation method is low, in the process of calculating the spent fuel transportation amount, the spent fuel assembly transportation amount of a nuclear power station is calculated only manually, and when the transportation amount of a plurality of nuclear power stations is calculated, the efficiency is low, and the accuracy is difficult to guarantee.
Disclosure of Invention
In order to improve accuracy and efficiency of nuclear power station spent fuel transportation quantity calculation and comprehensively calculate transportation quantities of a plurality of nuclear power station spent fuels, the application provides a calculation method and a system for making a nuclear power station spent fuel transportation plan.
The calculation method and the system for formulating the spent fuel transportation plan of the nuclear power station adopt the following technical scheme:
screening and obtaining the export possible amount of each type of component of each nuclear power plant meeting all receiving conditions of each receiving facility according to the component detailed information and the receiving facility basic information, and calculating and obtaining the export possible total amount of each type of component of each nuclear power plant meeting all receiving conditions of each receiving facility according to the export possible amount; wherein the component is the minimum transportation unit of the spent fuel;
calculating the receivable amount of each type of component which can receive the receiving condition of each receiving facility according to the basic information of the receiving facility;
determining an actual total transportation amount of each type of component transported to each receiving facility according to the total transportation amount and the receivable amount, and calculating the actual total transportation amount of each type of component transported by each nuclear power plant and the actual receiving amount of each type of component received by each receiving facility according to the actual total transportation amount by using a fair scheduling algorithm;
and calculating the outward movement component of each type of component of each nuclear power station according to the actual outward movement quantity and the actual receiving quantity.
By adopting the technical scheme, the first total amount of all nuclear power station conveying assemblies and the second total amount of all receiving facility receiving assemblies are counted, the actual total amount of transportation is determined, the actual outward transportation amount of the assemblies required to be conveyed by each nuclear power station and the actual receiving amount of each receiving facility receiving assembly are calculated according to the actual total amount of transportation and a fair scheduling algorithm, the outward transportation amount of each nuclear power station conveying the assemblies to each receiving facility in each year is further calculated, the first time of transportation is carried out to each outward transportation amount, the multi-year transportation plan of spent fuel transportation is finally obtained, various data required by the spent fuel transportation plan are counted and calculated through programs, the accuracy and the planning efficiency of the planning scheme are effectively improved, the spent fuel transportation plan of a plurality of nuclear power stations to a plurality of receiving facilities is completed simultaneously, and the transportation planning scheme is relatively comprehensive.
Further, calculating an actual outward transportation amount of each type of component transported by each nuclear power plant and an actual receiving amount of each type of component received by each receiving facility according to the actual total transportation amount by using a fair scheduling algorithm, including:
said actual total amount of traffic when transporting k-type components to the nth receiving facility
Equal to the receivable amount S of a type k component kn When the method is used:
defining the actual export capacity of each nuclear power plant for transporting each type of component under all reception conditions at each receiving facility as
Wherein the content of the first and second substances,
represents the number of k-type components actually carried by the ith nuclear power plant under all reception conditions at the nth receiving facility; calculating the actual receiving quantity of each type of component received by each receiving facility
Wherein the content of the first and second substances,
representing the number of k-type components actually received by the nth receiving facility;
when the actual total volume of transportation
Equal to the total amount of exportable of k type components
When the method is used:
screening in each nuclear power plant for satisfaction of said first attribute of said reception condition of the corresponding n-th receiving facility, calculating a first quantity thereof, and calculating a first total quantity of all of said first quantity under said reception condition of each of said receiving facilities based on said first quantity, said first total quantity being said actual outside traffic E' ki ；E′ ki Representing the number of k-type components actually carried by the ith nuclear power plant under the condition that all components meeting the first attribute can be transported;
defining the actual receiving quantity of each type of component received by each receiving facility as
Calculating the actual outward transportation amount of each type transported by each nuclear power station
And E' ki K 'of component rear K type component' ki (ii) a Wherein, K' ki Representing the pool occupation ratio after the ith nuclear power plant transports the k-type components;
according to the pool proportion K' ki Calculating K 'of proportion of pool' ki First variance Q of k The first equation of variance is:
wherein, O' k Denotes the pool proportion K' ki Average value of (d); i represents the total number of the nuclear power plants;
calculating the first variance Q according to a second formula and the first variance calculation formula k When the value is minimum, the actual outward transportation amount
A value of (d); wherein the second formula is:
calculating the actual receiving quantity of the n-th receiving facility receiving k type
Component of type k rear component of pool fraction P' kn ；
According to the proportion P 'of the pool' kn Calculating the pool fraction P 'of k type components after each of the receiving facility receives k type components' kn Second variance W of k The second variance calculation formula is:
wherein, G' k Denotes the pool proportion P 'of each receiving facility' kn Average value of (a); n represents the total number of receiving facilities;
calculating the second variance W according to a first formula and the second variance calculation formula k When the value is minimum, the actual receiving quantity
A value of (d); wherein the firstThe formula is as follows:
by adopting the technical scheme, the actual external transportation amount of each nuclear power station and the actual receiving amount of each receiving facility are determined by using a fair scheduling algorithm, if the first total amount is less than the second total amount, all spent fuel assemblies meeting the conditions are transported out, meanwhile, the water pools of each receiving facility after the assemblies are received are close in proportion, and each receiving facility can still keep certain capacity of the receiving assemblies; if the first total quantity is larger than or equal to the second total quantity, the unit water pools of the nuclear power stations after the assemblies are conveyed are enabled to be close to each other while the receiving quantity of each receiving facility is maximized, and each nuclear power station can continuously store the spent fuel assemblies discharged from the reactor of the nuclear power station so as to avoid full load of the water pools of the nuclear power stations due to uneven transportation.
Further, the calculating the external transportation component of each type of component of each nuclear power plant according to the actual external transportation quantity and the actual receiving quantity includes:
said actual total amount of traffic when transporting k-type components to the nth receiving facility
Equal to the receivable amount S of a type k component kn The method comprises the following steps:
the ith station delivers an outbound component E of type k components to the nth receiving facility kin Equal to the nth nuclear power station
Actual shipment volume for actual delivery of k-type components under all reception conditions of a reception facility
When the actual total volume of transportation
Equal to the total amount of exportable of k type components
When the method is used:
the actual external traffic E 'according to the ith said nuclear power plant k-type component' ki With the ith said nuclear power plant transporting said outbound component E of type k components to the nth said receiving facility kin Establishing a first equation
Receiving the actual received quantity of k-type components according to the nth receiving facility
With the ith said nuclear power plant transporting said outbound component E of type k components to the nth said receiving facility kin Establishing a second equation
Calculating the external motion component E of the ith nuclear power station for conveying k-type components to the nth receiving facility according to the first equation and the second equation kin 。
By adopting the technical scheme, the number of the spent fuel assemblies of different types conveyed to each receiving facility by each nuclear power station is calculated, the specific transportation number is planned, and the accuracy of spent fuel transportation planning is further improved.
Further, the step of obtaining the export possible amount of each type of component of each nuclear power plant satisfying all receiving conditions of each receiving facility through screening according to the component detailed information and the receiving facility basic information, and obtaining the export possible total amount through calculation according to the export possible amount includes:
classifying each type of component in each nuclear power plant according to each first attribute according to the component detailed information and the first attribute; wherein the first attribute comprises an initial enrichment, a burn-up, and a cooling time of the component;
screening said first attribute satisfying each of said reception conditions of each of said reception facilities based on said first attribute and said reception conditions;
calculating the export-capable quantity of each type of component of each of the nuclear power plants, the export-capable quantity being equal to a total quantity of the first property components satisfying all of the receiving conditions of each of the receiving facilities.
Through adopting above-mentioned technical scheme, classify and gather and count the subassembly according to the first attribute of subassembly itself, when transporting the planning to the subassembly, compare first attribute earlier with the corresponding receiving condition who receives the facility, can confirm that the subassembly that this first attribute corresponds can transport, but the total quantity of this attribute subassembly is convenient for calculate various types of subassemblies in each nuclear power station outward transport volume.
Further, said determining an actual total amount of transportation of each type of component to each of said receiving facilities from said total amount of exportable and said receivable amount comprises:
if the total amount of outward transportation is greater than or equal to the acceptable amount, the actual total amount of transportation is equal to the acceptable amount;
if the total amount deliverable is less than the acceptable amount, the actual total amount shipped is equal to the total amount deliverable.
By adopting the technical scheme, the actual transportation total amount is determined before transportation, so that the spent fuel assemblies transported out of all nuclear power stations can be received by all receiving facilities, the situation that the residual spent fuel assemblies cannot enter the receiving facilities and need to be transported back to the residual spent fuel assemblies is avoided, and the accuracy of spent fuel assembly transportation is improved.
Further, the method also comprises the step of correcting the outward transportation amount according to the information of the transportation container; the correction method comprises the following steps:
screening the first attribute satisfying a restriction condition from the first attributes satisfying all the receiving conditions of each of the receiving facilities according to the transport container information; the limiting conditions are limiting conditions of initial enrichment, burn-up and cooling time of each transport container to the assembly;
calculating the export-capable quantity of each nuclear power plant, wherein the export-capable quantity is equal to the total quantity of components corresponding to the first attribute which simultaneously meets all the receiving conditions of each receiving facility and all the limiting conditions of each transport container.
Through adopting above-mentioned technical scheme, the restrictive condition who uses the transport container makes the screening to first attribute, makes the subassembly that waits to transport can both have the container to satisfy its condition and transport, but each outward transport volume homoenergetic in the assurance planning is transported by the transport container.
Further, the method further comprises:
the correcting the outward movement component according to the transport container information includes:
according to the corrected outward transportation amount of each nuclear power station, the m types of transportation containers corresponding to the maximum number of the components corresponding to the first attribute are preferentially used, and A is calculated km ×B km ×R≤E kin When it is established, A km The maximum integer value of (d); wherein A is km Representing the number of m kinds of said transport containers carrying k-type components, B km Representing the capacity of m kinds of said transport containers for loading k-type components, R representing the maximum transport frequency of each of said transport containers, E kin Representing the number of k-type components delivered by the ith nuclear power plant to the nth receiving facility;
additionally using said transport containers of type m', calculated such that A km′ ×B km′ ×R≤E kin -A km ×B km When XR is established, A km′ The maximum integer value of (d); wherein A is km′ Representing the number of m' types of said transport containers loaded with k types of components;
calculating an outbound component E 'for each type of component delivered by each said nuclear power plant to each said receiving facility after modification' kin (ii) a The calculation formula is E' kin ＝A km ×B km ×R+A km′ ×B km′ ×R。
By adopting the technical scheme, the number of the available containers in each year is counted, and the outward transportation amount and the actual transportation amount are corrected according to the available total loading amount of the containers, so that the requirement of full container transportation can be guaranteed for each outward transportation amount; in the planning of guaranteeing to transport the spent fuel subassembly simultaneously, available container quantity can satisfy the total second aspect that needs transported the spent fuel subassembly, this application provides a calculation system that nuclear power station spent fuel transportation plan was made, adopts following technical scheme: a calculation system for planning and making a nuclear power plant spent fuel transportation plan comprises: the nuclear power plant spent fuel transportation planning method comprises a memory, a processor and a computer program stored on the memory and capable of running on the processor, wherein the processor executes the computer program to realize the nuclear power plant spent fuel transportation planning calculation method.
In summary, the present application includes at least one of the following beneficial technical effects:
1. calculating the actual transportation total amount of components required to be transported by each nuclear power station and the actual receiving amount of the receiving components of each receiving facility according to the actual transportation total amount and a fair scheduling algorithm, further calculating the transportation component of each nuclear power station to each receiving facility, and performing data processing through a program and a preset algorithm to improve the calculation efficiency, accuracy and comprehensiveness of the spent fuel component transportation amount;
2. the method comprises the steps that each type of component in each nuclear power station is classified and summarized according to a first attribute, when the components are transported and planned, only whether the first attribute meets the receiving condition of a corresponding receiving facility or not needs to be judged, then the total amount of the components under the corresponding first attribute is calculated, and the outward transportation capacity of the components can be determined, and the calculation is convenient;
3. the outward movement amount and the actual transportation total amount are adjusted through the transportation container information, the requirement that each outward movement amount can meet the transportation of a full container is guaranteed, and the outward movement amount and the actual transportation total amount can be matched according to a preset container using method.
Drawings
FIG. 1 is a flow chart of a method for calculating the transportation quantity of spent fuel in a nuclear power plant according to an embodiment of the present application;
FIG. 2 is a flowchart of a method for calculating the transportation quantity of spent fuel in a nuclear power plant according to an embodiment of the present application;
fig. 3 is a schematic structural diagram of a computing system for planning the transportation of spent fuel in a nuclear power plant according to the present application.
Detailed Description
In order to make the objects, technical solutions and advantages of the present application more apparent, the present application is further described in detail below with reference to fig. 1-3 and the embodiments. It should be understood that the specific embodiments described herein are merely illustrative of and not restrictive on the broad application.
The embodiment of the application discloses a calculation method for formulating a nuclear power station spent fuel transportation plan, which is used for a calculation system for formulating a nuclear power station spent fuel transportation plan, and the method comprises the following steps:
screening and obtaining the outward transportation capacity of each type of component of each nuclear power station meeting all receiving conditions of each receiving facility according to the detailed component information and the basic receiving facility information, and calculating and obtaining the outward transportation total quantity of each type of component of each nuclear power station meeting all receiving conditions of each receiving facility according to the outward transportation capacity; wherein the component is the minimum transportation unit of the spent fuel;
calculating the receivable amount of each type of component which can receive the receiving condition of each receiving facility according to the basic information of the receiving facility;
determining an actual total transportation amount of each type of component transported to each receiving facility according to the total transportation amount and the receivable amount, and calculating the actual total transportation amount of each type of component transported by each nuclear power plant and the actual receiving amount of each type of component received by each receiving facility according to the actual total transportation amount by using a fair scheduling algorithm;
and calculating the outward movement component of each type of component of each nuclear power station according to the actual outward movement quantity and the actual receiving quantity.
Example one
Referring to fig. 1, as an implementation manner of the method for making the spent fuel transportation plan, the calculation method for making the spent fuel transportation plan of the nuclear power plant disclosed in this embodiment includes:
step S100, acquiring and updating unit pool information and component detailed information of the nuclear power station at intervals, and receiving facility basic information; updating unit pool information of the nuclear power stations and component detailed information of the nuclear power stations by each nuclear power station according to a preset time interval; the reception facility basic information is updated by each reception facility at a preset time interval.
The assemblies are minimum transportation units of spent fuel, the assembly types are various, and the stacking requirements corresponding to each assembly type are different. The unit pool information of the nuclear power station comprises nuclear power station pool capacity C, nuclear power station pool occupancy U, nuclear power station refueling plan information, nuclear power station special vacancy occupancy L and nuclear power station pool occupancy K,
the nuclear power station pool occupancy U is the capacity of storage components in the nuclear power station pool; the occupation amount L of the special vacant sites of the nuclear power station is that the outward transportation components cannot occupy the space and the special vacant sites are used for transferring and placing the spent fuel components in the reactor when the nuclear power station has an emergency, and the spent fuel components are in an occupied state by default under the general condition.
The component detailed information of the nuclear power plant comprises the type of the components of the nuclear power plant and first attributes of the components, wherein the first attributes of the components comprise initial enrichment, burnup and final unloading date T of the components in And a cooling time T 1 . The enrichment degree of the nuclear power station components and the accumulated fuel consumption of the nuclear power station components are used as judgment bases for receiving facility receiving conditions and loading of transport containers. Last unloading date T of nuclear power station component in The time of the last unloading of the assembly from the reactor of the nuclear power station and the assembly into a water pool of a nuclear power station unit is indicated, and the cooling time is determined by the date of the last unloadingT in And (6) calculating.
The refueling plan information of the nuclear power station comprises a refueling period, a refueling time point and a corresponding refueling amount, wherein the refueling time point can be calculated by the refueling period, and when the refueling time point is reached each time, the nuclear power station increases the spent fuel assembly according to the corresponding refueling amount and unloads the spent fuel assembly into the unit water pool. When the query time is manually input, acquiring all the refueling time points between the query time and the current time and corresponding refueling amount according to the query time, and calculating the total refueling amount between the query time and the current time; and if the query time is after the current time, the pool occupation is equal to the current pool occupation plus the total refueling amount, and the pool occupation ratio K of the nuclear power station is recalculated and updated.
The basic information of the receiving facility comprises the type of a receivable component, the capacity D of a receiving facility pool, the occupancy V of the receiving facility pool, the discharge plan information of the receiving facility, the occupancy Z of a receiving facility special vacancy and the occupancy P of the receiving facility pool, and the calculation formula of the occupancy P of the receiving facility pool is as follows
Receiving the occupation quantity Z of the special vacancy of the facility, wherein the occupation quantity Z is used for storing the spent fuel assemblies under other special conditions, and the spent fuel assemblies are defaulted to be in an occupied state under the general conditions; the receiving facility discharging plan information comprises a discharging period, discharging time points and corresponding discharging quantities, the discharging time points can be calculated by the discharging period, and when the discharging time points are reached at each time, the receiving facility moves the spent fuel assemblies which are processed according to the corresponding discharging quantities out of the water pool.
When the query time is manually input, acquiring all discharging time points and corresponding discharging amounts between the query time and the current time according to the query time, and calculating the total discharging amount between the query time and the current time; and if the query time is after the current time, enabling the occupation of the receiving facility pool to be equal to the occupation of the current receiving facility pool, reducing the total amount of the refuelling, and recalculating and updating the occupation ratio P of the receiving facility pool.
The receiving facility basic information further includes receiving conditions that are a limit range of initial enrichment, burn-up, and cooling time that the corresponding receiving facility can receive the component, and each receiving facility includes a plurality of different receiving conditions.
And S200, classifying and summarizing each type of assembly according to the first attribute of the assembly, counting the number corresponding to each type of assembly meeting each first attribute, and screening the first attribute meeting each receiving condition of each receiving facility according to each receiving condition of each receiving facility.
Step S300, calculating the export transportation capacity corresponding to the first attribute component meeting all the receiving conditions of each receiving facility in each nuclear power plant according to the screened first attribute meeting all the receiving conditions of each receiving facility
And calculating an export total amount of the first attribute components satisfying all the reception conditions of each reception facility in all the nuclear power plants based on the export total amount
Wherein the content of the first and second substances,
indicating the amount of export possible for the ith nuclear power plant to the nth receiving facility with respect to k-type components,
representing the total amount of shippable of all nuclear power plants with respect to type k components to the nth receiving facility.
Step S400, calculating the receivable quantity S of each type of components which can be received by each receiving facility according to the basic information of the receiving facility kn (ii) a Wherein S is kn Indicating the number of k-type components that can be received at the nth receiving facility.
Number of receivable components S kn The capacity D of a receiving facility pool, the stock V of receiving facility pool components and the occupancy Z of receiving facility special vacancy are calculated, and the calculation formula is as follows: s. the kn ＝D kn -V kn -Z kn (ii) a Wherein D is kn Representing the pool capacity, V, of k-type components of the nth receiving facility kn Representing the pool occupancy of k-type components of the nth receiving facility, Z kn Indicating the occupancy of a particular vacancy for the nth receiving facility k type component.
Step S500, according to the total amount of outward transportation of each type of component
And an acceptable quantity S kn Determining the actual total amount of transportation for each type of component
And calculating the actual outward transportation amount of each nuclear power station for transporting k-type components according to the pool proportion information of the nuclear power station and the pool proportion information of the receiving facility by using a fair scheduling algorithm
And each receiving facility receives the actual received amount of the k-type component
Wherein the content of the first and second substances,
representing the total amount of k-type components actually delivered by all nuclear power plants to the nth receiving facility,
representing the actual export volume of the ith nuclear power plant transporting k-type components to the nth receiving facility,
indicating that the nth receiving facility receives the actual received amount of the k-type component.
Determining an actual total quantity of shipments of k-type components to an nth receiving facility
The method comprises the following steps:
if it can be transported outside
Is greater than or equal to the receivable amount S kn Actual total amount of transportation
Is equal to the receivable quantity S kn ；
If it can be transported outside
Less than acceptable amount S kn Actual total amount of transportation
Equal to the total amount of transportation
The logic of the fair scheduling algorithm is as follows:
if the actual total amount of transportation
Is equal to the receivable quantity S kn ：
Defining the actual external transportation quantity of each nuclear power plant for transporting each type of component under all receiving conditions of each receiving facility as
Wherein, the first and the second end of the pipe are connected with each other,
represents the number of k-type components actually carried by the ith nuclear power plant under all receiving conditions at the nth receiving facility;
calculating the actual receiving quantity of each type of component received by each receiving facility
Wherein, the first and the second end of the pipe are connected with each other,
representing the number of k-type components actually received by the nth receiving facility;
if the actual total amount of transportation
Equal to the total amount of export shippable of k type components
When the method is used:
screening in each nuclear power plant first attributes satisfying reception conditions of the corresponding n-th receiving facility, calculating a first number thereof, and calculating a first total amount of all first numbers, an actual outward transport amount E 'under the reception conditions of the respective receiving facilities based on the first number' ki Is equal to a first total amount E' ki Representing the number of k-type components actually transported by the ith nuclear power plant under the condition that all components meeting the first attribute can be transported;
defining the actual receiving quantity of each type of component received by each receiving facility as
Calculating the actual outward transportation amount of each type transported by each nuclear power station
And E' ki K 'of component Back K type component' ki (ii) a Wherein, K' ki Representing the pool occupation ratio after the ith nuclear power plant transports the k-type components;
k 'according to the proportion of the pool' ki K 'is accounted for in calculation pond' ki First variance Q of k The first equation of variance is:
wherein, O' k Denotes pool ratio K' ki Average of (2)A value; i represents the total number of nuclear power plants;
calculating a first variance Q according to a second formula and a first variance calculation formula k Actual outward transportation volume at minimum value
A value of (d); wherein the second formula is:
calculating the actual receiving quantity of the n receiving facility receiving k type
Component of type k rear component of pool fraction P' kn ；
According to the proportion of a pool to P' kn Calculating pool fraction P 'of k-type components after each receiving facility receives k-type components' kn Second variance W of k The second variance calculation formula is:
wherein, G' k Denotes each reception facility pool proportion P' kn Average value of (a); n represents the total number of receiving facilities;
calculating the second variance W according to the first formula and the second variance calculation formula k When the value is minimum, the actual receiving amount
A value of (d); wherein the first formula is:
step S600, according to the actual outward transportation quantity of each type of component of each nuclear power station and the actual outward transportation quantity of each type of component of each receiving facilityThe external movement component E of each type of component conveyed by each nuclear power plant to each receiving facility is calculated kin 。
The calculation method comprises the following steps:
the number of components per outward component is noted as E kin ，E kin Representing the number of k-type components that the ith nuclear power plant delivers to the nth receiving facility.
Actual total volume of traffic when delivering k-type components to the nth receiving facility
Equal to the receivable amount S of a type k component kn The method comprises the following steps:
the ith nuclear power plant delivers an outbound component E of type k components to the nth receiving facility kin Equal to the actual export volume of the ith nuclear power plant actually transporting k-type components under all receiving conditions of the nth receiving facility
When the actual total amount of transportation
Equal to the total amount of export shippable of k type components
The method comprises the following steps:
establishing a first equation
That is, the sum of the outbound components of k-type components received by all receiving facilities is equal to the actual outbound amount of k-type components transported by all nuclear power plants when the components satisfying the first property of all receiving conditions can all be transported;
establishing a second equation
I.e. the sum of the outbound components of each plant carrying k-type components is equal to the real component of each receiving facility receiving k-type componentsAn inter-receiving amount;
finding the corresponding extrinsic motion component E of each i and n by a first equation and a second equation kin The value of (c).
In this embodiment, a first total amount that each nuclear power station can transport out a spent fuel assembly and a second total amount that each receiving facility can receive the spent fuel assembly are judged through various pieces of information in the nuclear power station and the receiving facility, after an actual total transportation amount is determined according to the first total amount and the second total amount, the actual total transportation amount is divided into a plurality of outward transportation components, each outward transportation component corresponds to the number of assemblies transported by one nuclear power station to one receiving facility, and total task allocation and stage task allocation are performed according to each outward transportation component, so that guidance is provided for transportation of the spent fuel assemblies of the plurality of nuclear power stations. In addition, due to the fact that the transportation of the spent fuel is planned for many years, all spent fuel assemblies stored in the pool of the nuclear power station at the current time are planned, the transportation of the spent fuel for many years can be planned, and the accuracy and the planning efficiency of the transportation planning of the spent fuel are improved.
For example, as shown in table 1, let k-type components include 10 types of first attributes in the nuclear power plant 1, where the 10 types of first attributes are (1), (2) \8230; (r), respectively, where the number of components corresponding to the first attribute (1) is 90, and the number of components corresponding to the remaining first attributes is 5.
Assuming that the nuclear power plant 2 includes 12 types of k-type components having the first attributes, the 12 types of first attributes are (1), (2) \8230; 8230
The number of the components corresponding to the first attribute (7) is 100, and the number of the components corresponding to the other first attributes is 5.
Table 1: screening according to the first attribute at each nuclear power station
The first attributes of the k-type components meeting the receiving condition of the receiving facility 1 are set to be four types (1), (2), (3) and (4); is full ofThe first attributes of the k-type components of the reception condition of the reception facility 2 are five (4), (5), (6), (7) and (8); the first attributes of the k-type components that satisfy the reception conditions at reception facility 3 share (8), (9), r,
Four kinds; first attributes of the k-type components that satisfy the reception conditions at reception facility 4 are common (9), in (c), and,
Four kinds; and the receivable amounts of the k-type components by the receiving facilities 1, 2, 3, 4 are 40, 50, 70, 50, respectively.
According to the above conditions, the export possible amount of components satisfying all the reception conditions of each receiving facility in each nuclear power plant and the export possible total amount of components satisfying all the reception conditions of each receiving facility in all the nuclear power plants can be obtained, as shown in table 2:
table 2: the amount of export and total amount of export for each receiving facility for each nuclear power plant
Referring to table 3, the actual total amount of transportation is determined, in which case, with respect to the receiving facility 1, the total amount of exportable is greater than the receivable amount, the actual total amount of transportation is equal to 40:
the number of k-type components transported by the nuclear power plant 1 to the receiving facility 1 is
The number of k-type components transported by the nuclear power plant 2 to the receiving facility 1 is
At this time
With respect to the receiving facility 2, the total amount of exportable is greater than the acceptable amount, the total amount of actual transportation is equal to 50:
the number of k-type components transported by the nuclear power plant 1 to the receiving facility 2 is
The nuclear power plant 2 delivers to the receiving facility 2 a number of components of type k
At this time
With respect to the receiving facility 3, the total amount of exportable is less than the receivable amount:
the first attributes of the nuclear power plant 1 satisfying all the receiving conditions of the receiving facility 3 include (8), (9) and (r), and the first attributes of the nuclear power plant 2 satisfying all the receiving conditions of the receiving facility 3 include (8), (9),
With respect to the receiving facility 4, the total amount of export is less than the acceptable amount:
first attributes of nuclear power plant 1 that satisfy all receiving conditions at receiving facility 4 are (9), r, and first attributes of nuclear power plant 2 that satisfy all receiving conditions at receiving facility 4 are (9), r,
First attributes satisfying all reception conditions of reception facility 3 and reception facility 4 are (8), (9), r (c),
In total, the actual external transportation volume of the nuclear power plant 1 is the first total volume E 'of the components having the first attributes (8) and (9)' k1 =10, the actual shipment volume of the nuclear power plant 2 is (8), (9), in r,
Of assemblies of' k2 ＝25。
Actual reception quantity of the receiving facility 3
The actual receiving quantity of the receiving facility 4 is
Table 3: the export component of each receiving facility for each nuclear power plant
Calculating the pool occupation ratio of the k type components (the design capacity is 200, the special vacancy occupation is 0, and the initial pool occupation is 135) after the nuclear power plant 1 transports the k type components:
pool proportion of k-type components of a nuclear power plant 1
Calculating the pool occupancy of the k-type component after the nuclear power plant 2 has shipped the k-type component (the design capacity is 200, the special vacancy occupancy is 0, and the initial pool occupancy is 155)
Pool proportion of k-type components of a nuclear power plant 2
Calculating the variance of pool proportion of the nuclear power plant 1 and the nuclear power plant 2 when K' k1 ＝K′ k2 The difference between time and space is minimum to obtain
And
after the receiving facilities 1, 2, 3 and 4 receive the k-type components, the pool occupation ratio of the k-type components is calculated (the initial occupation and the special vacancy occupation are both 0):
receiving the pool occupancy =1 for facility 1;
pool occupancy =1 for the receiving facility 2;
calculating the variance of the pool ratio of the receiving facilities 3 and 4, and minimizing the variance value to obtain
Can be calculated according to the above formulas
And
i.e. the outbound component of each nuclear power plant carrying k-type components to each receiving facility.
Example two
Referring to fig. 2, after step S100, the method further includes:
and step S700, acquiring and updating the transport container information at intervals. The transport container information comprises container parameters, container quantity A, container loading quantity B, container available time and maximum loading frequency R.
The container parameters include the container type m, the type of component that the container can be loaded with. The server obtains the container parameters in real time and classifies the container parameters according to the types of the components which can be loaded by the server. When the query time is manually input, the container parameters and the available time of the container are obtained according to the query time, and the quantity A of the available transport containers at the time point is output km Wherein A is km Indicating the available number of mth transport containers capable of loading the kth container.
After step 300, the method further comprises:
and step S800, correcting the outward movement amount of each type of assembly according to the information of the transport container.
The correction method comprises the following steps:
screening first attributes meeting the limiting conditions from first attributes meeting all receiving conditions of each receiving facility according to the transport container information; wherein the limiting conditions are the limiting conditions of initial enrichment, burn-up and cooling time of each transport container to the assembly;
and calculating the corrected outward transportation capacity of each nuclear power station, wherein the outward transportation capacity is equal to the total quantity of the components corresponding to the first attribute which simultaneously meets all receiving conditions of each receiving facility and all limiting conditions of each transport container.
After step S600, the method further includes:
step S900, correcting the external transportation amount according to the transportation container information; the correction method comprises the following steps:
according to the corrected outward transportation capacity of each nuclear power station, the m types of transportation containers corresponding to the maximum number of the components corresponding to the first attribute are preferentially used, and A is calculated km ×B km ×R≤E kin When it is established, A km The maximum integer value of (d); wherein A is km Representing the number of m types of transport containers carrying k types of components, B km Denotes the capacity of m kinds of transport containers for loading k types of components, R denotes the maximum transport frequency of each transport container, E kin Representing the number of k-type components delivered by the ith nuclear power plant to the nth receiving facility;
additional use of m' type transport containers, calculated such that A km′ ×B km′ ×R≤E kin -A km ×B km When XR is established, A km′ The maximum integer value of (d); wherein A is km′ Representing the number of m' kinds of shipping containers that load k-type components;
calculating an outbound component E 'for each type of component each nuclear power plant delivers to each receiving facility after modification' kin (ii) a The calculation formula is E' kin ＝A km ×B km ×R+A km′ ×B km′ ×R。
In this embodiment, each export component of each nuclear power station is corrected according to the type of the available container through the transportation container information acquired in real time, so that each export component can meet the requirement of full container transportation.
The embodiment of the application also discloses a calculation system for making the nuclear power station spent fuel transportation plan, and the system can be installed on any type of functional equipment, such as a smart phone, a tablet computer, a computer or other mobile equipment with a data processing function.
Referring to fig. 3, the system includes a memory 100, a processor 200, and a computer program stored in the memory 100 and executable on the processor 200, and the processor 200 executes the computer program to implement the method for calculating the transportation amount of spent fuel at a nuclear power plant in the first embodiment and the second embodiment of the present application.
The system can be installed in a plurality of functional devices, and can be respectively arranged in each nuclear power station, each receiving facility or each worker, and the nuclear power stations, the receiving facilities or the workers can obtain the information stored and calculated by the system according to the system. The information between the memories in the systems can be updated synchronously, so that the results of the computer programs executed by the systems are the same.
The foregoing is a preferred embodiment of the present application and is not intended to limit the scope of the application in any way, and any features disclosed in this specification (including the abstract and drawings) may be replaced by alternative features serving equivalent or similar purposes, unless expressly stated otherwise. That is, unless expressly stated otherwise, each feature is only an example of a generic series of equivalent or similar features.
Claims (7)
1. A calculation method for making a nuclear power station spent fuel transportation plan is characterized by comprising the following steps:
screening and obtaining the outward transportation capacity of each type of component of each nuclear power plant meeting all receiving conditions of each receiving facility according to the component detailed information and the basic information of the receiving facility, and calculating and obtaining the outward transportation total capacity of each type of component of each nuclear power plant meeting all receiving conditions of each receiving facility according to the outward transportation capacity; wherein the component is the minimum transportation unit of the spent fuel;
calculating the receivable amount of each type of component which can receive the receiving condition of each receiving facility according to the basic information of the receiving facility;
determining an actual total transportation amount of each type of component transported to each receiving facility according to the total transportation amount and the receivable amount, and calculating the actual total transportation amount of each type of component transported by each nuclear power plant and the actual receiving amount of each type of component received by each receiving facility according to the actual total transportation amount by using a fair scheduling algorithm; wherein: if it can be transported outside
Is greater than or equal to the receivable amount S kn Actual total amount of transportation
Is equal to the receivable quantity S kn (ii) a If can be transported outside
Less than an acceptable amount S kn Actual total amount of transportation
Is equal toTotal amount of export transportation
Calculating the outward transportation component of each type of component of each nuclear power station according to the actual outward transportation quantity and the actual receiving quantity;
calculating the actual external transportation amount of each type of component transported by each nuclear power plant and the actual receiving amount of each type of component received by each receiving facility according to the actual total transportation amount by using a fair scheduling algorithm, wherein the method comprises the following steps:
said actual total amount of traffic when transporting k-type components to the nth receiving facility
Equal to the receivable amount S of a type k component kn When the method is used:
defining the actual external transportation quantity of each nuclear power plant for transporting each type of component under all receiving conditions of each receiving facility as
Wherein, the first and the second end of the pipe are connected with each other,
represents the number of k-type components actually carried by the ith nuclear power plant under all reception conditions at the nth receiving facility;
calculating the actual receiving quantity of each type of component received by each receiving facility
Wherein the content of the first and second substances,
representing the number of k-type components actually received by the nth receiving facility;
when it is at homeTotal actual transportation amount
Equal to the total amount of exportable of k type components
When the method is used:
screening first attributes meeting the receiving conditions of the nth receiving facility in each nuclear power station, calculating a first quantity of the first attributes, and calculating a first total quantity of all the first quantities under the receiving conditions of each receiving facility according to the first quantity, wherein the first total quantity is the actual outward transportation quantity; defining the actual outward transportation quantity of the ith nuclear power plant k type component to be E 'under the condition of ensuring that the components meeting the first attribute can be all transported' ki ；E′ ki Representing the number of k-type components actually carried by the ith nuclear power plant under the condition that all components meeting the first attribute can be transported;
defining the actual receiving quantity of each type of component received by each receiving facility as
Calculating a pool proportion K 'of K type components after each component of each type of actual external transportation quantity transported by each nuclear power plant' ki (ii) a Wherein, K' ki Representing the pool occupation ratio after the ith nuclear power plant transports the k-type components;
according to the proportion K of the pool' ki Calculating K 'of proportion of pool' ki First variance Q of k The first equation of variance is:
wherein, O' k Represents the ratio K 'of the pool' ki Average value of (a); i represents the total number of the nuclear power plants;
according to a second formula and the firstA variance calculation formula for calculating the first variance Q k When the value is minimum, the actual outward transportation amount
A value of (d); wherein the second formula is:
calculating the actual receiving quantity of the n-th receiving facility receiving k type
Component of type k rear component of pool fraction P' kn ；
According to the proportion P 'of the pool' kn Calculating the pool fraction P 'of k type components after each of the receiving facility receives k type components' kn Second variance W of k The second variance calculation formula is:
wherein, G' k Representing the pool fraction P 'of each of the receiving facilities' kn Average value of (d); n represents the total number of said receiving facilities;
calculating the second variance W according to the first formula and the second variance calculation formula k When the value is minimum, the actual receiving amount
A value of (d); wherein the first formula is:
2. the method of claim 1, wherein said calculating an export component for each type of component for each said nuclear power plant based on said actual export volume and said actual received volume comprises:
said actual total amount of traffic when transporting k-type components to the nth receiving facility
Equal to the receivable amount S of a type k component kn When the method is used:
the ith station delivers an outbound component E of type k components to the nth receiving facility kin Equal to the actual delivery of k-type components by the ith nuclear power plant under all reception conditions at the nth receiving facility
When the actual total volume of transportation
Equal to the total amount of exportable of k type components
The method comprises the following steps:
e 'of k type component according to ith nuclear power plant' ki Conveying the outbound component E of k-type components with the ith said nuclear power plant to the nth said receiving facility kin The relationship of (a) establishes a first equation:
receiving the actual received quantity of k-type components according to the nth receiving facility
The outbound shipment of k-type components with the ith said nuclear power plant to the nth said receiving facilityQuantity E kin Establishes a second equation:
calculating according to the first equation and the second equation to obtain the external motion component E of k-type components transported by the ith nuclear power station to the nth receiving facility kin 。
3. The calculation method for planning the transportation of spent fuel in a nuclear power plant according to claim 1, wherein the step of obtaining the export-capable quantity of each type of component of each nuclear power plant satisfying all the receiving conditions of each receiving facility through screening according to the component detailed information and the receiving facility basic information, and obtaining the export-capable total quantity of each type of component of each nuclear power plant satisfying all the receiving conditions of each receiving facility through calculation according to the export-capable quantity comprises:
classifying each type of component in each nuclear power plant according to each first attribute according to the component detailed information and the first attribute; wherein the first attribute comprises an initial enrichment, a burnup, and a last discharge date of the component;
screening said first attribute satisfying each of said reception conditions of each of said reception facilities based on said first attribute and said reception conditions; wherein the receiving condition is a limit range of initial enrichment, burn-up and cooling time of the receivable component by the receiving facility, the cooling time being calculated from the last discharge date; calculating, as an exportable total amount, a total amount of each of the exportable quantities equal to the first attribute components satisfying the exportable quantity reception condition for each type of component of all of the nuclear power plants of each of the receiving facilities.
4. The method of claim 1, wherein said determining an actual total amount of transportation of each type of component to each of said receiving facilities from said total amount of exportable and said receivable amounts comprises: if the total amount of outward transportation is greater than or equal to the acceptable amount, the actual total amount of transportation is equal to the acceptable amount;
if the total amount of shippable external is less than the acceptable amount, the actual total amount of shipment is equal to the total amount of shippable external.
5. The method of claim 3, further comprising modifying the shipment-capable quantity based on the shipping container information; the correction method comprises the following steps:
screening the first attribute satisfying a restriction condition from the first attributes satisfying all the receiving conditions of each of the receiving facilities according to the transport container information; the limiting conditions are the limiting conditions of initial enrichment degree, fuel consumption and cooling time of each transportation container to the assembly;
calculating the corrected export-allowable quantity of each nuclear power plant, wherein the export-allowable quantity is equal to the total quantity of components corresponding to the first attribute which simultaneously satisfies all the receiving conditions of each receiving facility and all the limiting conditions of each transport container.
6. The method of claim 5, further comprising:
the correcting the outward movement component according to the transport container information includes:
according to the corrected outward transportation quantity of each nuclear power station, the m types of the transportation containers corresponding to the maximum number of the components corresponding to the first attribute are preferentially used, and A is calculated km ×B km ×R≤E kin When it is established, A km The maximum integer value of (d); wherein, A km Representing the number of m kinds of said transport containers carrying k-type components, B km Representing the capacity of m kinds of said transport containers for loading k-type components, R representing the maximum transport frequency of each of said transport containers, E kin Representing the number of k-type components delivered by the ith nuclear power plant to the nth receiving facility;
additionally using said transport containers of type m', calculated such that A km′ ×B km′ ×R≤E kin -A km ×B km When x R is established, A km′ The maximum integer value of (d); wherein A is km′ Representing the number of m' types of said transport containers loaded with k types of components;
calculating an outbound component E 'for each type of component shipped by each of the nuclear power plants to each of the receiving facilities after the correction' kin (ii) a The calculation formula is E' kin ＝A km ×B km ×R+A km′ ×B km′ ×R。
7. A calculation system for planning and making a nuclear power plant spent fuel transportation plan comprises: the memory, the processor and the computer program stored in the memory and capable of running on the processor are characterized in that the processor, when executing the computer program, implements a calculation method for nuclear power plant spent fuel transportation planning according to any one of claims 1 to 6.
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