CN116130128A - Spent fuel storage grillwork and method and device for making loading scheme of spent fuel storage grillwork - Google Patents
Spent fuel storage grillwork and method and device for making loading scheme of spent fuel storage grillwork Download PDFInfo
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- CN116130128A CN116130128A CN202310011614.9A CN202310011614A CN116130128A CN 116130128 A CN116130128 A CN 116130128A CN 202310011614 A CN202310011614 A CN 202310011614A CN 116130128 A CN116130128 A CN 116130128A
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- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
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- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/40—Arrangements for preventing occurrence of critical conditions, e.g. during storage
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
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- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention provides a method and a device for formulating a spent fuel storage grillwork and a loading scheme thereof, wherein the formulating method comprises the following steps: the method comprises the steps of sorting N types of spent fuel assemblies according to reactivity, dividing the N types of spent fuel assemblies into M large types, forming M groups of spent fuel assemblies which are formed by at least one group of each type, forming M multiplied by N minimum arrangement units in a storage grid, wherein each group of spent fuel assemblies occupy one storage grid, periodically arranging the plurality of minimum arrangement units in the storage grid, forming a plurality of spent fuel storage grid arrangement schemes according to positions of the spent fuel assemblies in the minimum arrangement units and numerical values of M, M and N, calculating overall reactivity of the spent fuel assemblies in each arrangement scheme, and selecting the spent fuel storage grid arrangement scheme with the lowest overall reactivity or lower overall reactivity as a final spent fuel storage grid arrangement scheme. The invention can improve the economy of the spent fuel storage grillwork under the condition of meeting the design requirement of most of discharged spent fuel assemblies of a target reactor core stored by the spent fuel storage grillwork.
Description
5 technical field
The invention relates to the technical field of nuclear industry safety, in particular to a spent fuel storage grillwork and a method and a device for making a loading scheme of the spent fuel storage grillwork.
Background
In a 0-nuclear power plant, a spent fuel storage pool is an important facility for fuel operation and storage,
its primary function is to safely store fuel assemblies, including unirradiated fresh fuel assemblies, irradiated refueling assemblies and spent fuel assemblies that are no longer in stack for use, as well as potentially broken assemblies, etc. Spent fuel discharged from the core has strong radioactivity and large decay heat, and thus needs to be stored by a wet method.
The 5 nuclear power plant spent fuel storage pool is generally divided into two areas, wherein an I area grid is used for storing new fuel assemblies before stacking, unloading fuel assemblies of a reactor core when the reactor is shut down unexpectedly and the spent fuel assemblies which cannot be stored in an II area when the burnup does not reach the limit value requirement, and a new fuel assumption is adopted in critical safety design. Zone II storage shelves designs employ burn-up credit design techniques, i.e., each shelf is used to store spent 0 fuel assemblies at the same initial enrichment (burn up reaches a specified limit).
In order to improve the economy of wet storage, advanced spent fuel storage adopts a dense storage mode, namely, the storage space is reduced, the storage capacity is improved, and thus, higher requirements are placed on critical safety control of a storage system.
In the prior critical safety optimization design of the spent fuel pool grillwork, 5 methods such as interval control, fixed neutron absorbing material control and the like are generally adopted, for example, 201210574788.8 'a critical safety control method of the spent fuel pool grillwork without confidence boron', 2016104212446 'a spent fuel storage small chamber', a novel method for controlling the critical safety of the spent fuel pool grillwork, which is applied by China nuclear power engineering Co., ltd., are adopted,
201710815388.4 "a spent fuel storage rack"; 2015105484759 of Shanghai nuclear engineering institute of research and design application is "0 system for storing spent fuel with an inserted neutron absorber", 201710114428.2 "a neutron absorber for a spent fuel storage grid", 2017101137486 "a method for non-equidistant arrangement of connecting pieces of storage cavities of a spent fuel storage grid", 2021106612181 "a reticular sandwich structure storage cavity for dense storage of spent fuel", and the like.
There is no critical safety optimization design developed for the arrangement of spent fuel assemblies in storage grillwork.
Disclosure of Invention
Aiming at the defects in the prior art, the invention provides a method for formulating a loading scheme of a spent fuel storage grid, which can improve the economy of the spent fuel storage grid under the condition of meeting the design requirement of most of discharged spent fuel assemblies of a target reactor core stored by the spent fuel storage grid; the device for realizing the formulation method and the spent fuel storage grillwork designed by the final spent fuel storage grillwork arrangement scheme determined by the method or the device are also correspondingly provided.
The technical scheme adopted for solving the technical problems of the invention is as follows:
the invention provides a method for formulating a loading scheme of a spent fuel storage grillage, which comprises the following steps of
The method comprises the following steps:
the N spent fuel assemblies are ranked by reactivity size,
dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, forming a minimum M multiplied by N arrangement unit in a storage grid by at least one group of spent fuel assemblies in each category, wherein M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum placement units are periodically arranged in the storage grid to form a spent fuel storage grid placement scheme, the plurality of spent fuel storage grid placement schemes are formed according to the positions of the spent fuel assembly groups in the minimum placement units and the numerical values of M, m and n,
the overall reactivity of the spent fuel assemblies in each spent fuel storage rack arrangement is calculated, and the spent fuel storage rack arrangement with the lowest overall reactivity or lower overall reactivity is selected as the final spent fuel storage rack arrangement.
Optionally, in the minimum arrangement unit, if the type of spent fuel assembly with the highest reactivity comprises a plurality of groups of spent fuel assemblies, the plurality of groups of spent fuel assemblies are arranged in a pairwise non-adjacent way,
if the most reactive type of spent fuel assembly comprises a group of spent fuel assemblies, the group of spent fuel assemblies is not adjacently arranged with each group of spent fuel assemblies of the second most reactive type of spent fuel assemblies.
Optionally, forming a plurality of spent fuel storage grillwork arrangement schemes according to the positions of the spent fuel assembly groups in the minimum arrangement unit and the numerical values of M, m and n specifically comprises:
m is 2, 4, 3, 6 and 9,
when M is taken to be 2, four groups of spent fuel assemblies which are two groups of spent fuel assemblies are formed into a minimum arrangement unit of 2 multiplied by 2 in the storage grillwork, and a spent fuel storage grillwork arrangement scheme is formed,
when M is taken to be 4, four groups of spent fuel assemblies formed by four groups of spent fuel assemblies form a minimum arrangement unit of 2 multiplied by 2 in the storage grillwork, six spent fuel storage grillwork arrangement schemes are formed in a conformal way,
when M is taken to be 3, six groups of spent fuel assemblies which are formed by three groups and two groups of each group are formed into a minimum arrangement unit of 2 multiplied by 3 in the storage grillwork, twelve spent fuel storage grillwork arrangement schemes are formed,
when M is taken to be 6, six groups of spent fuel assemblies which are formed by six groups of spent fuel assemblies are formed in each group, a minimum arrangement unit of 2 multiplied by 3 is formed in the storage grillwork, sixteen spent fuel storage grillwork arrangement schemes are formed in a conformal manner,
when M is 9, nine groups of spent fuel assemblies formed by each group form a minimum arrangement unit of 3 multiplied by 3 in the storage grillwork, and eleven spent fuel storage grillwork arrangement schemes are formed.
Optionally, the ranked spent fuel assemblies are divided into M categories of substantially equal number per category.
Optionally, calculating the overall reactivity of the spent fuel assembly in each spent fuel storage grid arrangement specifically includes:
and calculating the nuclide components of the spent fuel assemblies according to the spent fuel assemblies with the highest reactivity in each type of spent fuel assemblies in the spent fuel storage grillwork arrangement scheme, and calculating the overall reactivity of the spent fuel assemblies in the spent fuel storage grillwork arrangement scheme according to the nuclide components of each type of spent fuel assemblies in the spent fuel storage grillwork arrangement scheme.
Optionally, the calculating the nuclide composition of each type of spent fuel assembly according to the spent fuel assembly with the highest reactivity in the spent fuel assemblies in the spent fuel storage grid arrangement scheme specifically comprises the following steps:
according to the initial enrichment degree, the unloading burnup depth and the reactor core irradiation history characteristics of the spent fuel assembly with the maximum reactivity in each type of spent fuel assembly, adopting the conservative combination of the nuclide component calculation parameters for critical safety analysis to calculate the nuclide component of the spent fuel assembly with the maximum reactivity as the nuclide component of the spent fuel assembly.
Alternatively, the overall reactivity of the spent fuel assemblies in each spent fuel storage grid arrangement is calculated using a spent fuel storage grid critical calculation model.
Optionally, the method further comprises: a minimum burnup limit at different initial enrichments is set for each type of spent fuel assembly of the final spent fuel storage grid arrangement.
The invention also provides a device for making the loading scheme of the spent fuel storage grillwork, which comprises the following steps:
a sequencing module for sequencing N spent fuel assemblies input by a user according to the reactivity,
the arrangement scheme forming module is electrically connected with the ordering module and is used for dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, a plurality of groups of spent fuel assemblies which are formed by at least one group of M categories, M multiplied by N minimum arrangement units are formed in the storage grid, each group of spent fuel assemblies occupies one storage grid, and M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum arrangement units are periodically arranged in the storage grillwork to form a spent fuel storage grillwork arrangement scheme, and according to the positions of the spent fuel assembly groups in the minimum arrangement units and the numerical values of M, m and n, a plurality of spent fuel storage grillwork arrangement schemes are formed,
and the calculation and selection module is used for calculating the overall reactivity of the spent fuel assemblies in each spent fuel storage grid arrangement scheme and selecting the spent fuel storage grid arrangement scheme with the lowest or lower overall reactivity as the final spent fuel storage grid arrangement scheme.
The invention also provides a spent fuel storage grillwork, which is obtained by designing a structure, a neutron absorbing material and a structural material of the spent fuel storage grillwork according to the final spent fuel storage grillwork arrangement scheme obtained by the preparation method or the preparation device.
The method for formulating the loading scheme of the spent fuel storage grillwork can determine the optimal alternate arrangement scheme of the high-reactivity spent fuel assemblies and the low-reactivity spent fuel assemblies under the condition that the design requirement of the vast majority of discharged spent fuel assemblies of a target reactor core stored by the spent fuel storage grillwork is met, so that the overall reactivity of the spent fuel storage grillwork is reduced, the center distance of adjacent storage units is reduced, the storage space is saved, and the economy of the spent fuel storage grillwork is improved on the premise of ensuring the critical safety of the spent fuel storage grillwork.
Drawings
FIG. 1 is a spent fuel storage grid loading scenario formed from 4 reactive fuel assemblies.
FIG. 2 is a schematic illustration of one minimum placement unit of the 2X 2 type formed by two reactive fuel assemblies;
FIG. 3 is a schematic illustration of a minimum placement unit of the type 2X 2 formed from four reactive fuel assemblies;
FIG. 4 is a schematic illustration of a minimum placement unit of the type 2X 3 formed from three reactive fuel assemblies;
FIG. 5 is a schematic illustration of a minimum placement unit of the type 2X 3 formed from six reactive fuel assemblies;
FIG. 6 is a schematic illustration of a minimum placement unit of the 3X 3 type formed by nine reactive fuel assemblies.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
In the description of the present invention, it should be noted that the orientation or positional relationship indicated by "upper" or the like is based on the orientation or positional relationship shown in the drawings, and is merely for convenience and simplicity of description, and is not meant to indicate or imply that the apparatus or element to be referred to must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, the terms "first," "second," and "second" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood by those skilled in the art in specific cases.
The invention provides a method for formulating a loading scheme of a spent fuel storage grillwork, which comprises the following steps:
the N spent fuel assemblies are ranked by reactivity size,
dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, forming a minimum M multiplied by N arrangement unit in a storage grid by at least one group of spent fuel assemblies in each category, wherein M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum placement units are periodically arranged in the storage grid to form a spent fuel storage grid placement scheme, the plurality of spent fuel storage grid placement schemes are formed according to the positions of the spent fuel assembly groups in the minimum placement units and the numerical values of M, m and n,
the overall reactivity of the spent fuel assemblies in each spent fuel storage rack arrangement is calculated, and the spent fuel storage rack arrangement with the lowest overall reactivity or lower overall reactivity is selected as the final spent fuel storage rack arrangement.
The invention also provides a device for making the loading scheme of the spent fuel storage grillwork, which comprises the following steps:
a sequencing module for sequencing N spent fuel assemblies input by a user according to the reactivity,
the arrangement scheme forming module is electrically connected with the ordering module and is used for dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, a plurality of groups of spent fuel assemblies which are formed by at least one group of M categories, M multiplied by N minimum arrangement units are formed in the storage grid, each group of spent fuel assemblies occupies one storage grid, and M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum arrangement units are periodically arranged in the storage grillwork to form a spent fuel storage grillwork arrangement scheme, and according to the positions of the spent fuel assembly groups in the minimum arrangement units and the numerical values of M, m and n, a plurality of spent fuel storage grillwork arrangement schemes are formed,
and the calculation and selection module is used for calculating the overall reactivity of the spent fuel assemblies in each spent fuel storage grid arrangement scheme and selecting the spent fuel storage grid arrangement scheme with the lowest or lower overall reactivity as the final spent fuel storage grid arrangement scheme.
The invention also provides a spent fuel storage grillwork, which is obtained by designing a structure, a neutron absorbing material and a structural material of the spent fuel storage grillwork according to the final spent fuel storage grillwork arrangement scheme obtained by the preparation method or the preparation device.
Example 1:
the invention provides a method for formulating a loading scheme of a spent fuel storage grillwork, which comprises the following steps:
the N spent fuel assemblies are ranked by reactivity size,
dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, forming a minimum M multiplied by N arrangement unit in a storage grid by at least one group of spent fuel assemblies in each category, wherein M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum placement units are periodically arranged in the storage grid to form a spent fuel storage grid placement scheme, the plurality of spent fuel storage grid placement schemes are formed according to the positions of the spent fuel assembly groups in the minimum placement units and the numerical values of M, m and n,
the overall reactivity of the spent fuel assemblies in each spent fuel storage rack arrangement is calculated, and the spent fuel storage rack arrangement with the lowest overall reactivity or lower overall reactivity is selected as the final spent fuel storage rack arrangement.
In this embodiment, in the minimum arrangement unit, if the type of spent fuel assembly with the greatest reactivity includes multiple sets of spent fuel assemblies, the multiple sets of spent fuel assemblies are arranged in a pairwise non-adjacent manner,
if the most reactive type of spent fuel assembly comprises a group of spent fuel assemblies, the group of spent fuel assemblies is not adjacently arranged with each group of spent fuel assemblies of the second most reactive type of spent fuel assemblies.
That is, in the spent fuel storage rack, the case where the two highest reactivity spent fuel assemblies are adjacent is excluded, so that the highest reactivity spent fuel assemblies are arranged alternately with the low reactivity spent fuel assemblies.
In addition, when the N spent fuel assemblies are ranked according to reactivity, 5 should exclude spent fuel assemblies that have greater individual reactivity and greater differences from other assemblies.
In this embodiment, according to the positions of the spent fuel assembly groups in the minimum arrangement unit and the numerical values of M, m and n, a plurality of spent fuel storage grillwork arrangements are formed, which specifically includes:
m is 2, 4, 3, 6 and 9,
0 when M is taken to be 2, forming a minimum arrangement unit of 2 multiplied by 2 in the storage grillwork by using four groups of spent fuel assemblies which are formed by two groups of spent fuel assemblies in each group, forming a spent fuel storage grillwork arrangement scheme,
when M is taken to be 4, four groups of spent fuel assemblies formed by four groups of spent fuel assemblies form a minimum arrangement unit of 2 multiplied by 2 in the storage grids, six spent fuel storage grids 5 frame arrangement schemes are formed in a conformal manner,
when M is taken to be 3, six groups of spent fuel assemblies which are formed by three groups and two groups of each group are formed into a minimum arrangement unit of 2 multiplied by 3 in the storage grillwork, twelve spent fuel storage grillwork arrangement schemes are formed,
when M is 6, six groups of spent fuel assemblies formed by six groups of spent fuel assemblies are formed in a 0 storage grillwork to form a minimum arrangement unit of 2 multiplied by 3, sixteen spent fuel storage grillwork arrangement schemes are formed in a conformal manner,
when M is 9, nine groups of spent fuel assemblies formed by each group form a minimum arrangement unit of 3 multiplied by 3 in the storage grillwork, and eleven spent fuel storage grillwork arrangement schemes are formed.
5, i.e., ultimately forming 45 spent fuel storage grid arrangements.
In other embodiments, the values and numbers of M, m and n may be established based on field practices.
In this embodiment, the ranked spent fuel assemblies are divided into M classes with substantially the same number of each class. Specific divisions are exemplified as follows:
0 if 20 spent fuel assemblies exist on site, after the 20 spent fuel assemblies are sequenced according to the reactivity, when M is taken to be 2, the 1 st to 10 th are classified into a first class, and the 11 th to 20 th are classified into a second class; when M is taken to be 3, the M can be divided into a first class from 1 st to 7 th, a second class from 8 th to 14 th, a third class from 15 th to 20 th, a first class from 1 st to 6 th, a second class from 7 th to 13 th, a third class from 14 th to 20 th, a first class from 1 st to 7 th, a second class from 8 th to 13 th, and a third class from 14 th to 20 th; the cases of M taking 4, 6 and 9 and so on are not repeated again.
After being divided into categories, each category is regarded as an enveloping spent fuel assembly group, each enveloping spent fuel assembly group occupies one storage cell in the minimum arrangement unit, and each enveloping spent fuel assembly group in the minimum arrangement unit can have a plurality, and the plurality occupies a plurality of storage cells correspondingly.
In this embodiment, calculating the overall reactivity of the spent fuel assembly in each spent fuel storage grid arrangement specifically includes:
and calculating the nuclide components of the spent fuel assemblies according to the spent fuel assemblies with the highest reactivity in each type of spent fuel assemblies in the spent fuel storage grillwork arrangement scheme, and calculating the overall reactivity of the spent fuel assemblies in the spent fuel storage grillwork arrangement scheme according to the nuclide components of each type of spent fuel assemblies in the spent fuel storage grillwork arrangement scheme.
In this embodiment, the calculating, according to the most reactive spent fuel assembly of each type of spent fuel assemblies in the spent fuel storage rack arrangement scheme, the nuclide composition of the spent fuel assemblies specifically includes:
according to the initial enrichment degree, the unloading burnup depth and the reactor core irradiation history characteristics of the spent fuel assembly with the maximum reactivity in each type of spent fuel assembly, adopting the conservative combination of the nuclide component calculation parameters for critical safety analysis to calculate the nuclide component of the spent fuel assembly with the maximum reactivity as the nuclide component of the spent fuel assembly.
The conservative combination of nuclide component calculation parameters for critical safety analysis refers to a conservative analysis method based on burnup credit for a fuel management scheme to be adopted by a target reactor core, and takes the relatively conservative reactivity as a measure during critical safety analysis to determine the conservative combination of relevant parameters of irradiation history, including but not limited to component power, fuel temperature, coolant density and temperature, soluble boron concentration, burnable poison type and quantity and the like.
In this embodiment, the overall reactivity of the spent fuel assemblies in each spent fuel storage grid arrangement is calculated using a spent fuel storage grid critical calculation model.
In the reactivity analysis of the spent fuel assembly arrangement, the end effects introduced by the axial burnup profile should be considered. Accordingly, if a critical calculation model for describing the axial segments in detail is required to be adopted, in the calculation of the nuclide composition of each type of spent fuel assembly, the nuclide composition of each segment of the axial segment of the spent fuel assembly with the greatest reactivity should be calculated.
In this embodiment, the method further includes: based on the threshold analysis, a minimum burn-up limit at different initial enrichment is set for each type of spent fuel assembly of the final spent fuel storage grid arrangement.
The method for making the loading scheme of the spent fuel storage grillage of the embodiment comprises the following detailed steps:
s1: simulating a burnup management scheme of a target reactor core, and sequencing various unloading spent fuel assemblies to be loaded from large to small according to reactivity;
s2: removing individual spent fuel assemblies with larger reactivity, continuously dividing the residual discharged spent fuel assemblies into a plurality of groups according to the reactivity of the discharged spent fuel assemblies, wherein the quantity of each group of spent fuel assemblies is basically the same;
s3: selecting a group of spent fuel assemblies with the highest reactivity from each group of spent fuel assemblies as enveloping spent fuel assemblies;
s4: calculating the nuclide components of each enveloping spent fuel assembly selected in the step S3 by adopting the conservative combination of the nuclide component calculation parameters for critical safety analysis according to the initial enrichment degree, the unloading burnup depth and the reactor core irradiation history characteristics of each enveloping spent fuel assembly;
s5: placing each enveloped spent fuel assembly into a critical calculation model of a spent fuel storage grid for arrangement, determining minimum arrangement units according to the quantity of the enveloped spent fuel assemblies, and periodically arranging the minimum arrangement units to form the spent fuel storage grid;
s6: analyzing the change of the reactivity by adjusting the position of each enveloped spent fuel assembly in the minimum arrangement unit in S5, and determining the arrangement scheme with the lowest reactivity as an optimal arrangement scheme;
s7: for different numbers of grouping conditions, performing the optimal loading scheme analysis of S2-S6, and finally selecting the optimal loading scheme of the spent fuel storage grillwork of the target reactor core according to the complexity of arrangement and the effect of the reduction of the reactivity;
s8: the optimized loading scheme of the spent fuel storage grillage finally selected in the step S7 is developed, and the arrangement and adjustment of neutron absorbing materials and structural materials in the grillage are carried out so as to adapt to the optimized loading scheme of the spent fuel storage grillage finally selected;
s9: a critical safety limit analysis is performed for each spent fuel assembly placement location, and a minimum burnup limit at different initial enrichments is set for each spent fuel assembly placement location.
The embodiments of this patent are described in further detail below taking the design of a spent fuel storage rack of a nuclear power plant as an example.
In the nuclear power station unit, 8X 10 type grids are arranged in a spent fuel storage pool II area, in order to facilitate analysis and research of an optimized loading scheme, the 8X 10 type grids are adopted to conduct analysis and research of a 2X 2 configuration optimized loading scheme, the 8X 9 type grids are adopted to conduct analysis and research of a 2X 3 configuration optimized loading scheme, the 9X 9 type grids are adopted to conduct analysis and research of a 3X 3 configuration optimized loading scheme, and periodic boundary conditions are adopted to avoid excessive local reactivity caused by adjacent shallower burnup components of adjacent grids.
If the prior critical safety arrangement method is adopted, the effective increment factor of the zone II grid of the spent fuel storage pool under the normal working condition is 0.9091 +/-0.0005.
The specific analysis steps are as follows:
firstly, spent fuel assembly reactivity data of the reactor core discharged from the first cycle to the transition cycle and the balance cycle are respectively arranged. Under normal conditions, the number of spent fuel assemblies from the first cycle to the transition cycle discharge core is determined, but the spent fuel assemblies from the balance cycle discharge core are uncertainty, and increase in multiple with the increase in the number of the spent fuel assemblies subjected to the balance cycle, so that the spent fuel assembly reactivity data from the first cycle to the transition cycle and the balance cycle discharge core are required to be respectively arranged, the formed spent fuel storage grillwork is ensured to optimize the loading scheme, not only can the spent fuel assemblies from the first cycle to the transition cycle and the balance cycle discharge core be loaded, but also the spent fuel storage grillwork can be loaded with the spent fuel assemblies from the most balance cycle discharge core no matter how many balance cycles are subsequently subjected, so long as the total capacity of the spent fuel storage grillwork is enough.
The optimized loading scheme analysis takes into account the different configurations and the different number of reactivities to develop the analysis respectively.
The analysis of the 2X 2 configuration optimized loading scheme is divided into two cases of matching two kinds of reactive fuel assemblies and matching four kinds of reactive spent fuel assemblies, and each case respectively considers the expansion calculation analysis of the two enveloping spent fuel assemblies from the first circulation to the transition circulation and the balance circulation.
For the collocation of two kinds of reactive spent fuel assemblies, the arrangement is carried out according to the reactivity data, all unloading assemblies from the first circulation to the transition circulation and the balance circulation are divided into two parts according to the reactivity of the assemblies, the number of the assemblies of the two parts is equivalent, and the assemblies with the largest reactivity of each part are respectively taken as envelop assemblies of the spent fuel assemblies of the parts for calculation and analysis, so that nuclide composition calculation is carried out.
And under the condition of matching the four reactive spent fuel assemblies, arranging according to the reactivity data, dividing all unloading assemblies from a first cycle to a transition cycle and a balance cycle into 4 parts according to the reactivity of the assemblies, respectively taking the assemblies with the maximum reactivity of each part for calculation and analysis, and carrying out nuclide component calculation.
In the spent fuel storage rack, two reactive fuel assemblies may form two arrangements, the smallest arrangement unit of one of which is shown in fig. 1. The four reactive fuel assemblies may form six arrangements, one of which is shown in fig. 2 and the smallest arrangement of which is shown in fig. 3. And (3) respectively calculating the reactivity under two arrangements by adopting a critical safety calculation program.
The analysis of the 2X 3 configuration optimized loading scheme is divided into two cases of matching three reactive fuel assemblies and matching six reactive spent fuel assemblies, and the two envelopment spent fuel assemblies of the first cycle to the transition cycle and the balance cycle are respectively considered for unfolding calculation analysis in each case.
For the collocation of three kinds of reactive spent fuel assemblies, the arrangement is carried out according to the reactivity data, all unloading assemblies from the first circulation to the transition circulation and the balance circulation are divided into 3 parts according to the reactivity of the assemblies, the number of the assemblies of each part is equivalent, and the assemblies with the largest reactivity of each part are respectively taken as envelopment assemblies of the spent fuel assemblies of the part for calculation and analysis, so that nuclide composition calculation is carried out.
For the collocation of six reactive spent fuel assemblies, the arrangement is carried out according to the reactivity data, all unloading assemblies from the first circulation to the transition circulation and the balance circulation are divided into 6 parts according to the reactivity of the assemblies, the number of the assemblies of each part is equivalent, and the assemblies with the largest reactivity of each part are respectively taken as envelopment assemblies of the spent fuel assemblies of the part for calculation and analysis, so that nuclide composition calculation is carried out.
In the spent fuel storage rack, excluding the case where the two highest reactive components are adjacent, the three reactive fuel components can be collocated to form 12 schemes, one of which is shown in fig. 4. The arrangement of the 6 reactive fuel assembly collocations in the spent fuel storage grillwork excludes the situation that the two highest reactive assemblies are adjacent, and 16 reactive fuel assembly collocations are selected, one of which is shown in fig. 5. The fuel components of different fuel assemblies and the components of different segments in the axial direction are different, so that the materials in the calculation model are more arranged due to the different fuel components, and the colors of different materials show that the conditions are relatively similar, and are actually different materials. And (5) adopting a critical safety calculation program to calculate the reactivity under different arrangements respectively.
And analyzing the 3X 3 configuration optimized loading scheme, analyzing by considering the collocation condition of nine reactive spent fuel assemblies, and respectively analyzing by considering the expansion calculation of the two enveloping spent fuel assemblies from the first circulation to the transition circulation and the balance circulation.
According to the arrangement of the reactivity data, all the unloading assemblies from the first cycle to the transition cycle and the balance cycle are divided into 9 parts according to the reactivity of the assemblies, the number of the assemblies in each part is equivalent, and the assemblies with the largest reactivity in each part are respectively taken as enveloping assemblies of the spent fuel assemblies in the parts for calculation and analysis, so that nuclide composition calculation is carried out.
The arrangement of the nine reactive fuel assembly collocations in the spent fuel storage grillwork excludes the situation that the two highest reactive assemblies are adjacent, and 11 reactive fuel assembly collocations are selected, one of which is shown in fig. 6. The fuel components of different fuel assemblies and the components of different segments in the axial direction are different, so that the materials in the calculation model are more arranged due to the different fuel components, and the colors of different materials show that the conditions are relatively similar, and are actually different materials. And (5) adopting a critical safety calculation program to calculate the reactivity under different arrangements respectively.
Finally, the reactivity under different arrangements is compared:
the effective increment factor calculated by adopting two reactive fuel assembly schemes is 0.8896+/-0.0005 at the minimum, and the effective increment factor is reduced by 1950pcm;
the effective increment factor calculation result of the three reactive fuel assembly schemes is 0.8825 +/-0.0005 at the lowest, and the effective increment factor is reduced by 2660pcm;
the calculation result of the effective increment factors of the four reactive fuel assembly schemes is 0.8788+/-0.0005 at the minimum, and the effective increment factors are reduced by 3030pcm;
the effective increment factor calculation result of the six reactive fuel assembly schemes is 0.8793 +/-0.0005 at the minimum, and the effective increment factor is reduced by 2980pcm;
the calculated result of the effective increment factor by adopting the nine reactive fuel assembly schemes is 0.8763 +/-0.0005 at the minimum, and the effective increment factor is reduced by 3280pcm.
The reactivity difference of reaction 5 is small between different arrangements of the same number of reactive fuel assemblies analyzed. Considering the complexity of the loading arrangement and the resulting effect of reduced reactivity, four reactive fuel assembly loading schemes in a 2 x 2 configuration are recommended, and the effective increment factor reduction can reach more than 2900pcm in different arrangements.
Further analysis shows that under the optimized loading scheme, the center-to-center distance between adjacent storage units of the spent fuel storage grillage can be reduced to 226mm, and the effective increment factor calculation result is equivalent to that of 0 without considering the optimized loading scheme, so that the storage density can be increased by 12%.
Therefore, the method for formulating the loading scheme of the spent fuel storage grillwork can determine the optimal alternative arrangement scheme of the high-reactivity spent fuel assemblies and the low-reactivity spent fuel assemblies under the condition of meeting the design requirement of most of discharged spent fuel assemblies of a target reactor core stored by the spent fuel storage grillwork, thereby reducing the overall reactivity 5 of the spent fuel storage grillwork, reducing the center distance of adjacent storage units, saving the storage space and improving the economy of the spent fuel storage grillwork on the premise of ensuring the critical safety of the spent fuel storage grillwork.
Under the optimized loading scheme, the analysis of accident conditions, loading curves and the like can be further carried out, the analysis of the critical safety limit value of each spent fuel assembly arrangement position is carried out, the minimum burnup limit value under different initial enrichment degrees is set for each spent fuel assembly arrangement position, and the critical safety design of the spent fuel storage grillwork is completed completely 0.
Example 2:
the present embodiment provides a device for making a spent fuel storage grillwork loading scheme for implementing the method of embodiment 1, including: a 5 sorting module for sorting N spent fuel assemblies input by a user according to the reactivity,
the arrangement scheme forming module is electrically connected with the ordering module and is used for dividing the ordered spent fuel assemblies into M large categories, wherein M is more than or equal to 2 and less than N, a plurality of groups of spent fuel assemblies which are formed by at least one group of M categories, M multiplied by N minimum arrangement units are formed in the storage grid, each group of spent fuel assemblies occupies one storage grid, and M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum arrangement units are periodically arranged in the storage grillwork to form a spent fuel storage grillwork arrangement scheme, and according to the positions of the spent fuel assembly groups in the minimum arrangement units and the numerical values of M, m and n, a plurality of spent fuel storage grillwork arrangement schemes are formed,
and the calculation and selection module is used for calculating the overall reactivity of the spent fuel assemblies in each spent fuel storage grid arrangement scheme and selecting the spent fuel storage grid arrangement scheme with the lowest or lower overall reactivity as the final spent fuel storage grid arrangement scheme.
Specifically, the sequencing module is pre-stored with various spent fuel assembly numbers, reactivity data and the like of the reactor core discharged from the transition cycle and the equilibrium cycle in the first cycle in the nuclear reaction process. The sequencing module comprises an interaction sub-module which is used for interacting with a user and receiving the numbers of N spent fuel assemblies to be loaded, which are input by the user.
In the arrangement scheme forming module, an interactive interface can be arranged, M, m and n values input by a user are received, and a plurality of spent fuel storage grillwork arrangement schemes are generated according to M, m and n values input by the user.
The 45 types of spent fuel storage grillwork arrangement schemes of 2, 4, 3, 6 and 9 in total in the M of the embodiment 1 can be stored in advance, and the 45 types of spent fuel storage grillwork arrangement schemes can be directly generated according to N types of spent fuel assemblies input by a user.
Example 3:
the present embodiment provides a spent fuel storage rack, which is a final arrangement scheme of the spent fuel storage rack obtained according to the formulation method of embodiment 1 or the formulation device of embodiment 2, and is obtained by designing a structure, a neutron absorbing material and a structural material of the spent fuel storage rack.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.
Claims (10)
1. The method for formulating the loading scheme of the spent fuel storage grillwork is characterized by comprising the following steps of:
the N spent fuel assemblies are ranked by reactivity size,
dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, forming a minimum M multiplied by N arrangement unit in a storage grid by at least one group of spent fuel assemblies in each category, wherein M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum placement units are periodically arranged in the storage grid to form a spent fuel storage grid placement scheme, the plurality of spent fuel storage grid placement schemes are formed according to the positions of the spent fuel assembly groups in the minimum placement units and the numerical values of M, m and n,
the overall reactivity of the spent fuel assemblies in each spent fuel storage rack arrangement is calculated, and the spent fuel storage rack arrangement with the lowest overall reactivity or lower overall reactivity is selected as the final spent fuel storage rack arrangement.
2. The method for preparing a loading scheme for a spent fuel storage grillwork according to claim 1, wherein if a type of spent fuel assembly with the greatest reactivity comprises a plurality of groups of spent fuel assemblies in the minimum arrangement unit, the plurality of groups of spent fuel assemblies are arranged in a non-adjacent manner,
if the most reactive type of spent fuel assembly comprises a group of spent fuel assemblies, the group of spent fuel assemblies is not adjacently arranged with each group of spent fuel assemblies of the second most reactive type of spent fuel assemblies.
3. The method for making a spent fuel storage rack loading scheme according to claim 2, wherein forming a plurality of spent fuel storage rack arrangement schemes according to the positions of the spent fuel assembly groups in the minimum arrangement unit and the numerical values of M, m and n, specifically comprises:
m is 2, 4, 3, 6 and 9,
when M is taken to be 2, four groups of spent fuel assemblies which are two groups of spent fuel assemblies are formed into a minimum arrangement unit of 2 multiplied by 2 in the storage grillwork, and a spent fuel storage grillwork arrangement scheme is formed,
when M is taken to be 4, four groups of spent fuel assemblies formed by four groups of spent fuel assemblies form a minimum arrangement unit of 2 multiplied by 2 in the storage grillwork, six spent fuel storage grillwork arrangement schemes are formed in a conformal way,
when M is taken to be 3, six groups of spent fuel assemblies which are formed by three groups and two groups of each group are formed into a minimum arrangement unit of 2 multiplied by 3 in the storage grillwork, twelve spent fuel storage grillwork arrangement schemes are formed,
when M is taken to be 6, six groups of spent fuel assemblies which are formed by six groups of spent fuel assemblies are formed in each group, a minimum arrangement unit of 2 multiplied by 3 is formed in the storage grillwork, sixteen spent fuel storage grillwork arrangement schemes are formed in a conformal manner,
when M is 9, nine groups of spent fuel assemblies formed by each group form a minimum arrangement unit of 3 multiplied by 3 in the storage grillwork, and eleven spent fuel storage grillwork arrangement schemes are formed.
4. A method of formulating a spent fuel storage rack loading solution according to any one of claims 1-3, wherein the ranked spent fuel assemblies are divided into M categories of substantially equal number of each category.
5. A method of formulating a spent fuel storage rack loading solution according to any one of claims 1-3, wherein calculating the overall reactivity of the spent fuel assembly in each spent fuel storage rack arrangement solution comprises:
and calculating the nuclide components of the spent fuel assemblies according to the spent fuel assemblies with the highest reactivity in each type of spent fuel assemblies in the spent fuel storage grillwork arrangement scheme, and calculating the overall reactivity of the spent fuel assemblies in the spent fuel storage grillwork arrangement scheme according to the nuclide components of each type of spent fuel assemblies in the spent fuel storage grillwork arrangement scheme.
6. The method for making a loading scheme for a spent fuel storage rack according to claim 5, wherein the calculating the nuclide composition of each type of spent fuel assembly according to the spent fuel assembly with the highest reactivity in the spent fuel assemblies in the arrangement scheme of the spent fuel storage rack specifically comprises:
according to the initial enrichment degree, the unloading burnup depth and the reactor core irradiation history characteristics of the spent fuel assembly with the maximum reactivity in each type of spent fuel assembly, adopting the conservative combination of the nuclide component calculation parameters for critical safety analysis to calculate the nuclide component of the spent fuel assembly with the maximum reactivity as the nuclide component of the spent fuel assembly.
7. The method of claim 5, wherein the overall reactivity of the spent fuel assemblies in each spent fuel storage rack arrangement is calculated using a spent fuel storage rack threshold calculation model.
8. The method for making a spent fuel storage rack loading scheme according to any one of claims 1-3, further comprising: a minimum burnup limit at different initial enrichments is set for each type of spent fuel assembly of the final spent fuel storage grid arrangement.
9. A device for establishing a spent fuel storage grillwork loading scheme, comprising:
a sequencing module for sequencing N spent fuel assemblies input by a user according to the reactivity,
the arrangement scheme forming module is electrically connected with the ordering module and is used for dividing the ordered spent fuel assemblies into M major categories, wherein M is more than or equal to 2 and less than N, a plurality of groups of spent fuel assemblies which are formed by at least one group of M categories, M multiplied by N minimum arrangement units are formed in the storage grid, each group of spent fuel assemblies occupies one storage grid, and M is more than or equal to 2 and N is more than or equal to 2; a plurality of minimum arrangement units are periodically arranged in the storage grillwork to form a spent fuel storage grillwork arrangement scheme, and according to the positions of the spent fuel assembly groups in the minimum arrangement units and the numerical values of M, m and n, a plurality of spent fuel storage grillwork arrangement schemes are formed,
and the calculation and selection module is used for calculating the overall reactivity of the spent fuel assemblies in each spent fuel storage grid arrangement scheme and selecting the spent fuel storage grid arrangement scheme with the lowest or lower overall reactivity as the final spent fuel storage grid arrangement scheme.
10. A spent fuel storage grid, characterized in that the spent fuel storage grid is a final spent fuel storage grid arrangement scheme obtained by the formulation method according to any one of claims 1-8 or the formulation device according to claim 9, and the spent fuel storage grid is designed by means of structure, neutron absorbing material and structural material.
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