CN115910396A - Nuclide component analysis method and nuclide component analysis device for spent fuel assembly - Google Patents
Nuclide component analysis method and nuclide component analysis device for spent fuel assembly Download PDFInfo
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Abstract
The invention discloses a nuclide component analysis method of a spent fuel assembly, which comprises the following steps: rod position data of each burn-up point of the AO control rod set and the mechanical compensation control rod set in the reactor core in each fuel cycle is acquired respectively. And acquiring the number N of the calculation sections of the AO control rod set according to the rod position data of each burn-up point of the AO control rod set in each fuel cycle. Obtaining the maximum burn-up depth proportion Z of the mechanical compensation control rod group according to the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle k . The number of calculation sections N inserted according to the AO control rod group and the maximum burn-up depth ratio Z of the mechanical compensation control rod group k And carrying out burnup calculation on each axial section of the spent fuel assembly to obtain the nuclide composition of each axial section of the spent fuel assembly. The method can be used for analyzing the nuclide component of the spent fuel assembly, and the analysis result is accurate. The invention also relates toDisclosed is a nuclide component analysis device of a spent fuel assembly.
Description
Technical Field
The invention belongs to the technical field of nuclear industry, and particularly relates to a nuclide component analysis method and a nuclide component analysis device for a spent fuel assembly.
Background
Critical safety analysis is an important aspect of spent fuel handling, transportation or storage design, and is directly related to nuclear safety issues. The method for the burnup credit is used as a method for nuclear critical safety analysis, and is different from the traditional analysis method for considering spent fuel as new fuel with highest enrichment degree and without irradiation, the method for the burnup credit considers the overall reduction of reactivity caused by the increase of irradiation and cooling time of a reactor core of the fuel, and excavates certain calculation margin, so that the economy of nuclear equipment or nuclear facilities adopting the method for nuclear critical safety design is improved.
At present, a fuel consumption credit system method is adopted in the design of spent fuel storage systems of most nuclear power plants in China, and the fuel consumption credit system method is gradually applied to the nuclear critical safety design of a spent fuel post-treatment plant.
The critical safety analysis of spent fuel is carried out by a burn-up credit method, and reliable and conservative spent fuel nuclide components are determined firstly. At present, the nuclide component of the spent fuel is mainly obtained by a burn-up calculation method. Therefore, when the spent fuel nuclide component is analyzed, a set of parameter combination for calculating the burnup of the nuclide component is required to be selected. The combination includes, but is not limited to, power, fuel temperature, coolant density and temperature, soluble boron concentration, burnable poison type and quantity, etc. of the spent fuel assembly. Among other things, control rod insertion is also an important consideration. Control rods are typically inserted into the spent fuel assembly from top to bottom for compensating fuel consumption, adjusting power distribution and power levels, core trip, etc. The insertion of the control rod affects the accuracy of the fuel consumption calculation, and further affects the judgment of the reactivity of the spent fuel.
The current part of nuclear reactor types adopt a mechanical compensation operation mode. During operation in the mechanical compensation mode of operation, the control rod groups are alternately inserted into the core in a certain sequence, and the insertion sequence is periodically switched and alternated. Thus, the depth of insertion of the control rod set may be varied periodically during a fuel cycle. However, the variation law is complex, which presents great difficulty for the analysis of the nuclide composition of the spent fuel in considering the insertion of the control rod. In previous analytical work, the following criteria were generally used: and each axial section below a certain number of the axial sections of the spent fuel assembly performs fuel consumption calculation according to the condition of inserting the gray rod control rod. In practice, only a small proportion of the gray rod control rods are inserted into the spent fuel assembly in each axial section of the lower portion of the spent fuel assembly. This analysis method is too conservative, which overestimates the reactivity of spent fuel assemblies when using burnup credit in storage, transportation, and post-processing processes, and is not conducive to improving the economics of critical safety design.
At present, research and development personnel develop research and application in the aspect of application of a fuel consumption credit system of a spent fuel post-processing facility, but a related method or process is not provided for nuclide component analysis for critical safety analysis of a reactor spent fuel assembly in a mechanical compensation operation mode.
Disclosure of Invention
The invention aims to solve the technical problem of the prior art, and provides a nuclide component analysis method and a nuclide component analysis device for a spent fuel assembly.
According to an embodiment of the first aspect of the present invention, there is provided a nuclide composition analysis method for a spent fuel assembly, including:
s1: respectively acquiring rod position data of each burn-up point of an AO control rod group and a mechanical compensation control rod group in the reactor core in each fuel cycle,
s2, acquiring the calculation segment number N of the AO control rod group according to the rod position data of each burning point of the AO control rod group in each fuel cycle,
s3: obtaining the maximum burn-up depth proportion Z of the mechanical compensation control rod group according to the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle k ，
S4: the number of calculation sections N inserted according to the AO control rod group and the maximum burn-up depth ratio Z of the mechanical compensation control rod group k And carrying out burnup calculation on each axial section of the spent fuel assembly to obtain the nuclide composition of each axial section of the spent fuel assembly.
Preferably, in the step S1, acquiring rod position data of each burn-up point of the AO control rod group and the mechanical compensation control rod group in the core in each fuel cycle includes the following steps: and simulating the fuel circulation process of the core from the first circulation to the balance circulation in the mechanical compensation operation mode to obtain the rod position data of each burn-up point of the AO control rod group and the mechanical compensation control rod group in each fuel circulation.
Preferably, step S2 specifically includes: the method comprises the steps of obtaining the axial segmentation number of the spent fuel assembly, obtaining the maximum average insertion depth P of the AO control rod group according to rod position data of each combustion point of the AO control rod group in each fuel cycle, and determining the calculation segmentation number N of the AO control rod group according to the axial segmentation number of the spent fuel assembly and the maximum average insertion depth P.
Preferably, the maximum average insertion depth P of the AO control rod set is obtained according to rod position data of each burn-up point of the AO control rod set in each fuel cycle, and the method comprises the following steps: performing a burn-up depth weighted average calculation on the rod position data of the AO control rod set in each fuel cycle to find an average insertion depth P of the AO control rod set in each fuel cycle i Comparing said AO controlAverage insertion depth P of rod making group in each fuel circulation i And selecting the maximum value as the maximum average insertion depth P of the AO control bar set.
Preferably, determining the calculated number of segments N of the AO control rod group according to the number of axial segments of the spent fuel assembly and the maximum average insertion depth P comprises the following steps: and obtaining the corresponding relation between the axial sections and the rod position data of the AO control rod group according to the axial section number of the spent fuel assembly, and obtaining the axial section number corresponding to the maximum average insertion depth P of the AO control rod group according to the corresponding relation between the rod position data of the AO control rod group, namely the calculation section number N of the AO control rod group.
Preferably, in step S3, the maximum burn-up depth ratio Z of the mechanical compensation control rod group is obtained according to rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle k The method comprises the following steps: obtaining the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle, obtaining the corresponding relation between the axial segments and the rod position data of the mechanical compensation control rod group according to the axial segment number of the spent fuel assembly, obtaining the axial segment number corresponding to the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to the corresponding relation of the rod position data of the mechanical compensation control rod group, performing the weighted average calculation of the burn-up depth according to the axial segment number, and obtaining the burn-up depth proportion Z of the mechanical compensation control rod group in each fuel cycle ik Comparing the burn-up depth ratio Z of the mechanical compensation control rod set in each fuel cycle ik Selecting the maximum value as the maximum burn-up depth ratio Z of the mechanical compensation control rod set k 。
Preferably, the burn-up depth ratio Z ik The increased burnup depth is the proportion of the total burnup depth when the mechanical compensation control rod is inserted into each axial section of the spent fuel assembly.
Preference is given toIn step S4, the number of stages N of the insertion of the AO control rod group and the maximum burn-up depth ratio Z of the mechanical compensation control rod group are calculated k And carrying out fuel consumption calculation on each axial section of the spent fuel assembly, wherein the fuel consumption calculation method comprises the following steps: judging whether the axial subsection is the front N section of the upper end of the spent fuel assembly: if yes, carrying out fuel consumption calculation on the axial subsection according to calculation parameters of inserting AO control rods; if not, continuously judging whether the burn-up depth ratio of the axial section is between 100 and Z k Within the range: if yes, performing fuel consumption calculation on the axial subsection according to calculation parameters without inserting a control rod; and if not, performing fuel consumption calculation on the axial subsection according to the calculation parameters of the inserted mechanical compensation control rod.
Preferably, the method further comprises the steps of: s5: and obtaining the total ratio of each nuclide component in the spent fuel assembly through each axially segmented nuclide component.
According to an embodiment of the second aspect of the invention, a nuclide component analysis device for a spent fuel assembly is provided, which comprises a rod position data module, an AO rod group segmentation module, a burn-up ratio module and a burn-up calculation module, wherein the rod position data module is used for respectively acquiring rod position data of burn-up points of an AO control rod group and a mechanical compensation control rod group in a reactor core in each fuel cycle, the AO rod group segmentation module is connected with the rod position data module and is used for acquiring a calculation segment number N of the AO control rod group according to the rod position data of the burn-up points of the AO control rod group in each fuel cycle, and the burn-up ratio module is connected with the rod position data module and is used for acquiring a maximum burn-up depth ratio Z of the mechanical compensation control rod group according to the rod position data of the burn-up points of the mechanical compensation control rod group in each fuel cycle k The fuel consumption calculation module is connected with the AO rod group segmentation module and the fuel consumption proportion module and is used for calculating the number N of the segments according to the insertion of the AO control rod group and the maximum fuel consumption depth proportion Z of the mechanical compensation control rod group k Performing a burnup calculation on each axial segment of the spent fuel assembly to obtain each axial segment of the spent fuel assemblyNuclide component of (a).
Preferably, the AO rod set segmentation module comprises an axial segmentation unit, an average insertion depth unit and a determination unit, the axial segmentation unit is configured to obtain the number of axial segments of the spent fuel assembly, the average insertion depth unit is connected to the rod position data module and is configured to obtain the maximum average insertion depth P of the AO control rod set according to the rod position data of each burn-up point of the AO control rod set in each fuel cycle, and the determination unit is connected to the axial segmentation unit and the average insertion depth unit and is configured to determine the calculated number N of segments of the AO control rod set according to the number of axial segments of the spent fuel assembly and the maximum average insertion depth P.
Preferably, the burn-up ratio module comprises a maximum insertion depth unit, a corresponding unit, a segment determining unit, a burn-up depth ratio unit and a value selecting unit, wherein the maximum insertion depth unit is used for obtaining the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle, the corresponding unit is used for obtaining the corresponding relation between the axial segments and the rod position data of the mechanical compensation control rod group according to the number of the axial segments of the spent fuel assembly, the segment determining unit is connected with the corresponding unit and used for obtaining the axial segment number corresponding to the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to the corresponding relation, and the burn-up depth ratio unit is connected with the segment determining unit and used for obtaining the burn-up depth ratio Z of the mechanical compensation control rod group in each fuel cycle according to the axial segment number ik The value selecting unit is connected with the burn-up depth proportion unit and is used for comparing the burn-up depth proportion Z of the mechanical compensation control rod group in each fuel cycle ik Selecting the maximum value, namely the maximum burn-up depth ratio Z of the mechanical compensation control rod set k 。
Preferably, the fuel consumption calculation module comprises a judgment unit and a calculation unit, the judgment unit and the calculation unitThe calculation unit is connected and used for judging whether the axial subsection is the front N section of the upper end of the spent fuel assembly or not: if yes, sending a first signal to the computing unit, and if not, judging whether the burn-up depth ratio of the axial segment is 100% -Z k Within the range: if yes, sending a second signal to the calculating unit, if no, sending a third signal to the calculating unit, wherein the calculating unit is used for carrying out fuel consumption calculation on the axial section according to the calculation parameters of inserting the AO control rod when receiving the first signal, or carrying out fuel consumption calculation on the axial section according to the calculation parameters of not inserting the control rod when receiving the second signal, or carrying out fuel consumption calculation on the axial section according to the calculation parameters of inserting the mechanical compensation control rod when receiving the third signal.
According to the nuclide component analysis method of the spent fuel assembly, the rod position data of the AO control rod group and the rod position data of the mechanical compensation control rod group are respectively obtained, and the calculation segment number of the AO control rod group and the maximum burn-up depth proportion of the mechanical compensation control rod group are respectively obtained according to the rod position data of the AO control rod group and the rod position data of the mechanical compensation control rod group. And then, determining a calculation parameter of each axial segment according to the number of the calculation segments and the maximum burn-up depth ratio, and performing burn-up calculation according to the calculation parameter so as to obtain the nuclide component of each axial segment of the spent fuel assembly. Therefore, the method for analyzing the nuclide component of the spent fuel can analyze the nuclide component of the spent fuel assembly, reasonably and conservatively considers the actual operation condition of the reactor core, has accurate analysis result, can accurately judge the reactivity of the spent fuel assembly, and is further beneficial to improving the economy of critical safety design.
The nuclide component analysis method of the spent fuel assembly is particularly suitable for analyzing the nuclide component of the nuclear reactor spent fuel assembly in a mechanical compensation operation mode.
Drawings
FIG. 1 is a flow chart of a method of spent fuel nuclide analysis in some embodiments of the present invention;
FIG. 2a is a bar position data plot for AO control bar sets at each burn-up point in the core balancing cycle in some embodiments of the present invention;
FIG. 2b is a bar position data plot for gray rod control rod set 1 and gray rod control rod set 2 at each burn-up point in the core balancing cycle in accordance with some embodiments of the present invention;
FIG. 2c is a graph of rod position data for gray rod control rod set 3 and gray rod control rod set 4 at each burn-up point in the core balancing cycle, in accordance with some embodiments of the present invention.
Detailed Description
The technical solutions in the present invention will be described clearly and completely with reference to the accompanying drawings, and it is obvious that the described embodiments are some, but not all embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the scope of the present invention.
In the description of the present invention, it should be noted that the terms "upper", "lower", "upstream", "downstream", and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience and simplicity of description, and do not indicate or imply that the indicated device or element must be provided with a specific orientation, constructed 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" 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 is to be noted that, unless otherwise explicitly specified or limited, the terms "connected," "disposed," "mounted," "fixed," and the like are to be construed broadly, e.g., as being fixedly or removably connected, or integrally connected; either directly or indirectly through intervening media, or may be interconnected between two elements. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the description of the present invention, each unit and module referred to may correspond to only one physical structure, or may be composed of multiple physical structures, or multiple units and modules may be integrated into one physical structure; the units and modules may be implemented by software or hardware, for example, the units and modules may be located in a processor.
In the description of the present invention, functions, steps, etc., which are noted in the flowcharts and block diagrams of the present invention may occur in different orders from those noted in the drawings without conflict.
Example 1
Referring to fig. 1, the present invention discloses a nuclide component analysis method of a spent fuel assembly, including the following steps:
s1: rod position data of each burn-up point of the AO control rod set and the mechanical compensation control rod set in the reactor core in each fuel cycle is acquired respectively.
And S2, acquiring the number N of the calculation sections of the AO control rod group according to the rod position data of each burn-up point of the AO control rod group in each fuel cycle.
S3: obtaining the maximum burn-up depth ratio Z of the mechanical compensation control rod group according to the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle k 。
S4: according to the calculated number of sections N inserted by the AO control rod set and the maximum burn-up depth ratio Z of the mechanical compensation control rod set k And carrying out burnup calculation on each axial section of the spent fuel assembly to obtain the nuclide composition of each axial section of the spent fuel assembly.
The AO control rod group includes a plurality of black rod control rod groups, and the mechanical compensation control rod group includes a plurality of gray rod control rod groups. In the present embodiment, the AO control rod group in the core in the mechanical compensation operation mode is a group of black rod control rod groups. The mechanical compensation control rod group comprises four gray rod control rod groups, namely a gray rod control rod group 1, a gray rod control rod group 2, a gray rod control rod group 3 and a gray rod control rod group 4.
The mechanical compensation control rod group of the reactor core and the AO control rod group which can independently control the axial power distribution realize load tracking operation without regulating boron. In particular, the value of the four gray rod control rod sets and the design of the overlapping rod lifting program can ensure that the insertion of the AO control rod set leads the axial offset factor to be monotonically decreased. In the mechanically compensated mode of operation, the average coolant temperature at the designed power condition is maintained by using four sets of gray rod control rods. The rod control system controls the AO control rod group to ensure that the axial offset factor is basically kept unchanged in the whole load tracking operation period. The operator makes adjustments to the reactor coolant system boron concentration to account for long-term core burnup. Adjusting the boron concentration may also cause the two gray rod control rod sets to remain in a nearly fully extracted position, with the two gray rod control rod sets initially moving in a fully inserted position, and the AO rod set in a small number of inserted positions.
Further, in performing a critical safety analysis on the reactor spent fuel assembly, it is necessary to determine a reliable, conservative nuclide composition. However, the existing nuclide analysis method is too conservative, and when the method is used for performing the fuel consumption calculation on the spent fuel assembly, the fuel consumption calculation is performed on each axial section below a certain number of axial sections under the condition that a gray rod control rod is inserted, so that the reactivity of the spent fuel assembly is overestimated, and the economic efficiency of critical safety design is not improved favorably. The nuclide component analysis method needs to calculate the number N of sections according to the insertion of the AO control rod set (black rod) and the maximum burn-up depth ratio Z of the mechanical compensation control rod set (gray rod) k The calculation parameters of each axial segment are respectively determined, and the fuel consumption calculation is carried out according to the calculation parameters.
Therefore, the method can analyze the nuclide components of the spent fuel assembly, accurately judge the reactivity of the spent fuel assembly under the condition of ensuring the safety, and further improve the economy of critical safety design.
In this embodiment, the step S1 specifically includes the following steps: and simulating the fuel circulation process of the core from the first circulation to the balance circulation in the mechanical compensation operation mode to obtain the rod position data of each burn-up point of the AO control rod set and the mechanical compensation control rod set in each fuel circulation.
It should be noted that after the reactor core is started, three transition cycles are usually required to enter the equilibrium cycle. Therefore, in the present embodiment, the first cycle to the equilibrium cycle are the 1 st to 5 th cycles. To determine the rod position data for insertion of the AO control rod set and the mechanical compensation control rod set into the spent fuel assemblies, the core operating conditions from the first cycle to the equilibrium cycle in the mechanical compensation mode of operation may be simulated by the core calculation program. Specifically, in the core calculation program, the AO control rod group and the mechanical compensation control rod group are set to operate under the base load of the mechanical compensation operation mode, thereby obtaining the rod position data of each burn-up point in each burn-up cycle (i.e., 1 st to 5 th cycles) of the AO control rod group and the mechanical compensation control rod group.
Illustratively, as shown in FIGS. 2a, 2b and 2c, wherein FIG. 2a provides rod position data for AO control rod sets at each burn-up point in the core balancing cycle (i.e., cycle 5) under mechanical compensation mode base load control; FIG. 2b provides rod position data for gray rod control rod set 1 and gray rod control rod set 2 at each burn-up point in the core balance cycle under mechanical compensation mode of operation base load control; FIG. 2c provides rod position data for gray rod control rod set 3 and gray rod control rod set 4 at each burn-up point in the core balancing cycle under mechanical compensation mode of operation base load control.
More specifically, the core calculation program may be either ANC or Bamboo.
In this embodiment, the step S2 specifically includes the following steps:
the number of axial segments of the spent fuel assembly is obtained,
obtaining the maximum average insertion depth P of the AO control rod group according to the rod position data of each burn-up point of the AO control rod group in each fuel cycle,
and determining the number N of the calculated sections of the AO control rod group according to the number of the axial sections of the spent fuel assembly and the maximum average insertion depth P.
The method comprises the following steps of obtaining the maximum average insertion depth P of the AO control rod group according to rod position data of each burn-up point of the AO control rod group in each fuel cycle, and specifically comprises the following steps:
burn-in of rod position data for AO control rod set in each fuel cycleDegree weighted average calculation to find the average insertion depth P of the AO control rod set in each fuel cycle i ，
Comparing the average insertion depth P of the AO control rod set over each fuel cycle i And selecting the maximum value as the maximum average insertion depth P of the AO control bar group.
Further, the calculation segment number N of the AO control rod group is determined according to the axial segment number and the maximum average insertion depth P of the spent fuel assembly, and the method specifically comprises the following steps:
obtaining the corresponding relation between the axial subsection and the rod position data of the AO control rod group according to the axial subsection number of the spent fuel assembly,
and obtaining the axial segmentation number corresponding to the maximum average insertion depth P of the AO control rod set through the corresponding relation of the rod position data of the AO control rod set, namely obtaining the calculation segmentation number N of the AO control rod set.
It should be noted that, according to the critical safety analysis requirement of the spent fuel, the axial direction of the spent fuel assembly is equally divided into a plurality of axial segments, and each axial segment has the same axial length. Illustratively, the spent fuel assemblies are axially equally divided into 18 sections according to the critical safety analysis requirement of the spent fuel assemblies so as to establish the corresponding relation between the rod position data and the axial sections of the AO control rod group. Specifically, if the rod position of the AO control rod group in the active core segment is 264 steps, the rod position of each spent fuel assembly is converted into 14.67 steps in the axial direction, wherein the height of each section is 5.56%. According to the rod position data of each burn-up point of each fuel cycle of the AO control rod group (black rod) under the basic load control of the mechanical compensation operation mode, the average insertion depth P in each cycle is obtained by a burn-up depth weighted average method i (percentage, where i represents the number of cycles). Average insertion depth P of cycles 1 to 5 i 6.8%, 8.5%, 8.9%, 4.7%, 4.8%, respectively. Wherein, P i The maximum value of (d) was recorded as 8.9%. And determining the number of axial sections of the spent fuel assembly, which need to consider insertion of AO control rods (black rods), to be 2 in the fuel consumption calculation in an upward rounding mode according to the corresponding relation between the rod position data of the in-core control rods and the axial sections, namely, calculating the number of the sections N to be 2.
In this embodiment, the step S3 specifically includes the following steps:
obtaining the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle,
obtaining the corresponding relation between the axial sections and the rod position data of the mechanical compensation control rod group according to the number of the axial sections of the spent fuel assembly,
obtaining the axial segmentation number corresponding to the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle through the corresponding relation of the rod position data of the mechanical compensation control rod group,
according to the axial segment number, carrying out combustion depth weighted average calculation to obtain the combustion depth proportion Z of the mechanical compensation control rod group in each fuel cycle ik ，
Comparing burn-up depth ratios Z of mechanically compensated control rod sets in each fuel cycle ik Selecting the maximum value, namely the maximum burn-up depth ratio Z of the mechanical compensation control rod set k 。
It should be noted that the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle refers to: and the rod position data of each burn-up point in each cycle (namely 1 st to 5 th cycles) under the basic load control of the mechanical compensation operation mode of the mechanical compensation control rod set. And obtaining the maximum insertion depth (percentage) of the mechanical compensation control rod group (namely the gray rod control rod group) at each burnup point of each cycle according to the rod position data. Then, the corresponding relationship between the rod position data of the mechanical compensation control rod group and the axial segment is established, and the process is the same as that of the AO control rod group, which is not described herein again by way of example.
Further, according to the corresponding relation between the rod position data and the axial sections, the number of the axial sections, inserted by the mechanical compensation control rod group, of the spent fuel assemblies at each burn-up point in each fuel cycle is determined in an upward rounding mode. The mechanical compensation control rod group comprises a plurality of gray rod control rods. Further, the burn-up depth proportion Z of each axial subsection of each cycle inserted into the ash rod control rod group in the cycle burn-up is calculated ik (percentage, where i represents the number of cycles and k represents the axial step-wise sequencing of the active area of the fuel assembly), and the maximum Z for each cycle is calculated ik The value is noted as Z k 。
It should be noted that the burn-up depth ratio Z ik The increased burnup depth when the mechanical compensation control rods are inserted into each axial section of the spent fuel assembly accounts for the proportion of the total burnup depth. Specifically, the burn-up is calculated by a burn-up depth weighting method. When the burn-up depth is calculated, whether axial burn-up distribution of the spent fuel assembly is considered or not needs to be determined according to an application scenario. If the consideration is needed, an axial burnup envelope curve is determined firstly to obtain a burnup normalization factor Bk of each axial section, and then the burnup depth of each axial section to (Bu · Bk) is obtained according to the average burnup depth Bu of the spent fuel assembly. If not, each axial segment is burned to the burn-up depth of Bu.
Here, a spent fuel assembly with an initial enrichment of 4.95% and an assembly average fuel consumption of 42000MWd/tU is taken as an example. In the embodiment, the nuclide composition analysis of each axial section considers the axial envelope burn-up distribution of the spent fuel assembly, and the burn-up depths of each axial section are 21504, 33600, 41202, 43050, 46368, 46494, 46242, 46494, 46368, 46788, 46872, 46704, 47040, 43890, 42840, 38556 and 25830MWd/tU from top to bottom respectively. In the present embodiment, the burnup depth ratio corresponding to each axial segment is, for example, as shown in table 1:
TABLE 1 burn-up depth ratio of each axial segment into which a mechanically compensated control rod set is inserted in each fuel cycle
In the present embodiment, step S4: according to the calculated number of sections N inserted by the AO control rod set and the maximum burn-up depth ratio Z of the mechanical compensation control rod set k For spent fuelEach axial segment of the assembly is subjected to a burnup calculation. The method specifically comprises the following steps:
judging whether the axial subsection is the front N section of the upper end of the spent fuel assembly:
if yes, carrying out fuel consumption calculation on the axial subsection according to the calculation parameters of the inserted AO control rod;
if not, continuously judging whether the fuel consumption depth ratio of the axial segmentation is between 100 and Z k In the range: if yes, performing fuel consumption calculation on the axial subsections according to the calculation parameters without inserting a control rod; if not, performing fuel consumption calculation on the axial subsection according to the calculation parameters of the inserted mechanical compensation control rod.
It should be noted that, for a spent fuel assembly for which critical safety analysis needs to be performed, when performing burnup calculation, calculation parameters of nuclide components need to adopt a conservative combination suitable for use in the critical safety analysis to perform the burnup calculation for a given burnup depth. The conservative combination of the nuclide component calculation parameters refers to a conservative analysis method based on a fuel consumption credit system, and the conservative combination of the radiation history relevant parameters is determined by taking the conservative reactivity of the spent fuel assembly as a measure when the spent fuel assembly is used for critical safety analysis. Such conservative combinations include, but are not limited to, component power, fuel temperature, coolant density and temperature, soluble boron concentration, burnable poison type and quantity, and the like.
Specifically, after determining the calculation parameter type of each axial segment, the fuel economy calculation can be performed on each axial segment by an existing fuel economy calculation program. More specifically, the burnup calculation program may be either RMC or CASMO. For the fuel consumption calculation of different AO control rod group insertion states, different component calculation models are established in the fuel consumption calculation, for example, in the component model for performing the fuel consumption calculation by inserting the calculation parameters of the AO control rods, the AO control rods are inserted into the guide tubes of the components. For the fuel consumption calculation without inserting/inserting the mechanical compensation control rod in different fuel consumption depth proportion ranges, the fuel consumption calculation is realized by changing the rod inserting state function of the component calculation model or restarting calculation after changing the calculation model, and the applicable calculation function can be selected according to the functional characteristics of different programs.
Continuing with the example of a spent fuel assembly with an initial enrichment of 4.95% and an assembly average burn-up of 42000MWd/tU as described above. In this embodiment, the number of calculated segments N inserted by the AO control stick set is 2. Therefore, the sections 1-2 at the top of the spent fuel assembly are subjected to the fuel consumption calculation according to the calculation parameters of inserting AO control rods (black rods). Each of the other sections is ahead of its combustion depth (100% -Z) k ) Last Z of burning depth without any control rod inserted in range k And inserting a mechanical compensation control rod group (gray rod control rod group) into the range to perform burnup calculation, thereby obtaining the nuclide components of each axial segment which can be used for critical safety analysis. For the embodiment, from top to bottom, in the whole burnup range of the 2 nd to 8 th sections, the burnup calculation is carried out by inserting the gray rod control rod; in paragraphs 9 to 18, the burnup calculation is performed without inserting any control rod in the burnup ranges 3035, 6224, 8105, 12328, 16718, 21123, 23889, 26379, 27176, and 21329MWd/tU, and the burnup calculation is performed with inserting a gray rod control rod in the burnup ranges 43459, 40144, 38683, 34544, 29986, 25917, 20001, 16461, 11380, and 4501 Wd/tU. The concentration of the inserted gray rod control rods within the last portion of the burn-up depth allows for conservation of nuclide composition calculations.
In this embodiment, the method for analyzing the nuclide component of the spent fuel assembly further includes step S5: and obtaining the total ratio of each nuclide component in the spent fuel assembly through each axially segmented nuclide component.
Specifically, the average uranium and plutonium isotope ratio in the spent fuel assembly is taken as a conservative judgment and measurement standard of the reactivity of the spent fuel assembly, and an application scenario of critical safety design of a dissolving liquid of the spent fuel assembly after the spent fuel assembly is dissolved in a spent fuel reprocessing plant is taken as an example. Adding the fuel calculation components of each section of the spent fuel assembly in the axial direction to obtain the average uranium and plutonium isotope ratio of the assembly, wherein the residual percentage of U-235 in the total U is 1.870%; the mass ratio of Pu-239, pu-240, pu-241 and Pu-242 is 61.773:19.152:13.675:3.769.
in contrast, in the conventional nuclide component analysis method, the nuclide components obtained by performing the burnup calculation by inserting gray rod control rods are added to all burnup ranges of the stages 2 to 18, and the uranium and plutonium isotope ratios of the assembly average are obtained by similarly adding the fuel burnup components of the respective stages in the axial direction. The following results can be obtained, in which the remaining percentage of U-235 in the total U is 1.941%; the mass ratio of Pu-239, pu-240, pu-241 and Pu-242 is 63.328:18.178:13.475:3.389.
comparing the analysis results, it can be seen that in the average uranium and plutonium isotope ratio of the spent fuel assembly calculated by the method, the remaining percentage of U-235 in the total U is lower, the mass ratio of Pu-239 in the total Pu is higher, and the mass ratio of Pu-240 in the total Pu is lower. Therefore, under the same critical safety analysis condition, the average uranium and plutonium isotope ratio of the spent fuel assembly obtained by calculation by the method is lower in reactivity of the dissolving solution under the condition that critical safety can be guaranteed, so that the critical safety design can be more economical.
In addition, under the critical safety analysis conditions of the same uranium concentration, the same plutonium concentration and the same uranium and plutonium isotope ratio, the method is adopted to carry out nuclide component analysis on the spent fuel assembly, so that the minimum burnup limit value of the spent fuel assembly is determined, the minimum burnup limit value of the spent fuel assembly can be smaller, and therefore a spent fuel post-processing plant can process spent fuel assemblies with a larger burnup range, and the processing range of the spent fuel post-processing plant is improved.
The nuclide composition analysis method can be applied to nuclide composition analysis of a spent fuel assembly of the nuclear reactor in a mechanical compensation operation mode, and therefore critical safety design of the nuclear reactor is completed.
Example 2
The invention also discloses a nuclide component analysis device of the spent fuel assembly, which comprises: the device comprises a rod position data module, an AO rod group segmentation module, a fuel consumption proportion module and a fuel consumption calculation module.
The rod position data module is used for respectively acquiring rod position data of each burn-up point of an AO control rod group and a mechanical compensation control rod group in the reactor core in each fuel cycle. The AO rod group segmentation module is connected with the rod position data module and is used for controlling according to the AOAnd acquiring the calculated segment number N of the AO control rod group according to the rod position data of each burn-up point of the rod making group in each fuel cycle. The fuel consumption proportion module is connected with the rod position data module and used for acquiring the maximum fuel consumption depth proportion Z of the mechanical compensation control rod group according to the rod position data of each fuel consumption point of the mechanical compensation control rod group in each fuel cycle k . The fuel consumption calculation module is connected with the AO rod group segmentation module and the fuel consumption proportion module and is used for calculating the number N of the segments according to the insertion of the AO control rod group and the maximum fuel consumption depth proportion Z of the mechanical compensation control rod group k And carrying out burnup calculation on each axial section of the spent fuel assembly to obtain the nuclide composition of each axial section of the spent fuel assembly.
Specifically, the rod position data module may be a core calculation program, such as ANC or Bamboo. And modeling the reactor core through a rod position data module, and simulating a fuel circulation process from the first circulation to the balance circulation of the reactor core in a mechanical compensation operation mode to obtain rod position data of each burn-up point of the AO control rod group and the mechanical compensation control rod group in each fuel circulation. The rod position data module then transmits the rod position data to the AO rod set segmentation module.
In this embodiment, the AO rod set segmentation module includes an axial segmentation unit, an average insertion depth unit, and a decision unit. The axial segmentation unit is used for acquiring the number of axial segments of the spent fuel assembly. Specifically, the number of axial segments of the spent fuel assembly may be determined by an operator and then input into the axial segment unit. The axial segmentation unit sends the number of axial segments to the decision unit.
The average insertion depth unit is connected with the rod position data module and is used for obtaining the maximum average insertion depth P of the AO control rod group according to the rod position data of each burn-up point of the AO control rod group in each fuel cycle. Specifically, the average insertion depth unit performs a burn-up depth weighted average calculation on the rod position data of the AO control rod set in each fuel cycle after receiving the rod position data of each burn-up point of the AO control rod set in each fuel cycle to obtain the average insertion depth P of the AO control rod set in each fuel cycle i . Then, the average insertion depth isElement control rod set average insertion depth P within each fuel cycle by comparing AO i And selecting the maximum value, namely the maximum average insertion depth P of the AO control bar set. The average insertion unit is further adapted to send the maximum average insertion depth P of the AO control rod set to the decision unit.
Further, the determination unit is connected with the axial segmentation unit and the average insertion depth unit, and is used for determining the number of the calculated segments N of the AO control rod set according to the number of the axial segments of the spent fuel assemblies and the maximum average insertion depth P. Specifically, the judging unit obtains the corresponding relation between the axial sections and the rod position data of the AO control rod group according to the number of the axial sections of the spent fuel assemblies. Then, the judging unit obtains the axial segment number corresponding to the maximum average insertion depth P of the AO control rod group through the corresponding relation, namely the calculated segment number N of the AO control rod group.
In this embodiment, the fuel consumption proportion module includes a maximum insertion depth unit, a corresponding unit, a segment determination unit, a fuel consumption depth proportion unit, and a value selection unit. The maximum insertion depth unit is connected with the rod position data module and used for obtaining the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to the rod position data of each fuel consumption point of the mechanical compensation control rod group in each fuel cycle. The corresponding unit is used for obtaining the corresponding relation between the axial sections and the rod position data of the mechanical compensation control rod group according to the number of the axial sections of the spent fuel assembly. The segmentation determining unit is connected with the corresponding unit and used for obtaining the axial segmentation number corresponding to the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle through the corresponding relation. The burn-up depth proportion unit is connected with the segmentation determination unit and is used for obtaining the burn-up depth proportion Z of the mechanical compensation control rod group in each fuel cycle according to the number of axial segments ik . The value selecting unit is connected with the burn-up depth proportion unit and is used for comparing the burn-up depth proportion Z of the mechanical compensation control rod group in each fuel cycle ik Selecting the maximum value, namely the maximum burn-up depth ratio Z of the mechanical compensation control rod set k 。
In this embodiment, the burnup calculation module includes a determination unit and a calculation unit. The judging unit is connected with the calculating unit and used for judging whether the axial subsection is the front N section at the upper end of the spent fuel assembly: if yes, sending a first signal to the computing unit; if not, judging whether the burn-up depth proportion of the axial section is in the range of 100% -Zk: if yes, sending a second signal to the computing unit; if not, a third signal is sent to the calculation unit.
The calculation unit is used for carrying out fuel consumption calculation on the axial section according to the calculation parameters of the inserted AO control rods when receiving the first signal, or carrying out fuel consumption calculation on the axial section according to the calculation parameters of the inserted AO control rods when receiving the second signal, or carrying out fuel consumption calculation on the axial section according to the calculation parameters of the inserted mechanical compensation control rods when receiving the third signal.
In conclusion, the nuclide component analysis device of the spent fuel assembly can analyze the nuclide component of the spent fuel assembly, accurately judges the reactivity of the spent fuel assembly under the condition of ensuring the safety, and further improves the economy of critical safety design.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (13)
1. A nuclide composition analysis method for a spent fuel assembly is characterized by comprising the following steps:
s1: respectively acquiring rod position data of each burn-up point of the AO control rod group and the mechanical compensation control rod group in the reactor core in each fuel cycle,
s2, acquiring the calculation segment number N of the AO control rod group according to the rod position data of each burning point of the AO control rod group in each fuel cycle,
s3: acquiring rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycleMaximum burn-up depth ratio Z k ，
S4: the number of calculation sections N inserted according to the AO control rod group and the maximum burn-up depth ratio Z of the mechanical compensation control rod group k And carrying out burnup calculation on each axial section of the spent fuel assembly to obtain the nuclide composition of each axial section of the spent fuel assembly.
2. The method of claim 1, wherein the step S1 of obtaining rod position data for each burn-up point in each fuel cycle for AO control rod sets and mechanical compensation control rod sets in the core comprises the steps of:
and simulating the fuel circulation process of the core from the first circulation to the balance circulation in the mechanical compensation operation mode to obtain the rod position data of each burn-up point of the AO control rod set and the mechanical compensation control rod set in each fuel circulation.
3. The method according to claim 1, wherein step S2 specifically comprises:
acquiring the number of axial sections of the spent fuel assembly,
obtaining a maximum average insertion depth P of the AO control rod group according to rod position data of each burn-up point of the AO control rod group in each fuel cycle,
and determining the number N of the calculated sections of the AO control rod group according to the axial section number of the spent fuel assemblies and the maximum average insertion depth P.
4. A method according to claim 3, wherein deriving the maximum average insertion depth P of the AO control rod set from the rod position data of each burn-up point of the AO control rod set in each fuel cycle comprises the steps of:
performing a burn-up depth weighted average calculation on the rod position data of the AO control rod set in each fuel cycle to find an average insertion depth P of the AO control rod set in each fuel cycle i ，
Comparing said AO control rod set over each fuel cycleMean depth of insertion P i And selecting the maximum value as the maximum average insertion depth P of the AO control rod set.
5. A method according to claim 3, wherein determining the calculated number of segments N of the AO control rod cluster from the number of axial segments of the spent fuel assembly and the maximum average insertion depth P comprises the steps of:
obtaining the corresponding relation between the axial sections and the rod position data of the AO control rod group according to the axial section number of the spent fuel assembly,
and obtaining the axial segmentation number corresponding to the maximum average insertion depth P of the AO control rod group through the corresponding relation of the rod position data of the AO control rod group, namely obtaining the calculation segmentation number N of the AO control rod group.
6. The method of claim 1, wherein in step S3, the maximum burn-up depth ratio Z of the set of mechanical compensation control rods is obtained based on rod position data for each burn-up point of the set of mechanical compensation control rods in each fuel cycle k The method comprises the following steps:
obtaining the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to the rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle,
obtaining the corresponding relation between the axial sections and the rod position data of the mechanical compensation control rod group according to the number of the axial sections of the spent fuel assembly,
obtaining the axial segmentation number corresponding to the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle through the corresponding relation of the rod position data of the mechanical compensation control rod group,
according to the axial segment number, carrying out combustion depth weighted average calculation to obtain the combustion depth proportion Z of the mechanical compensation control rod group in each fuel cycle ik ，
Comparing the burnup of the set of mechanically compensated control rods for each fuel cycleDepth ratio Z ik Selecting the maximum value, namely the maximum burn-up depth ratio Z of the mechanical compensation control rod set k 。
7. The method of claim 6, wherein the burn-up depth ratio Z ik And increasing the burn-up depth to the proportion of the total burn-up depth when the mechanical compensation control rods are inserted into each axial section of the spent fuel assembly.
8. A method according to claim 1, characterized in that in step S4, the number of segments N calculated from the insertion of the AO control rod set and the maximum burn-up depth ratio Z of the mechanical compensation control rod set are used k And carrying out fuel consumption calculation on each axial section of the spent fuel assembly, wherein the fuel consumption calculation method comprises the following steps:
judging whether the axial subsection is the front N section of the upper end of the spent fuel assembly:
if yes, carrying out fuel consumption calculation on the axial subsection according to calculation parameters of inserting AO control rods;
if not, continuously judging whether the burn-up depth ratio of the axial section is between 100 and Z k Within the range: if yes, performing fuel consumption calculation on the axial subsection according to calculation parameters without inserting a control rod; and if not, performing fuel consumption calculation on the axial subsection according to the calculation parameters of the inserted mechanical compensation control rod.
9. The method according to any one of claims 1-8, characterized in that the method further comprises the step of:
s5: and obtaining the total ratio of each nuclide component in the spent fuel assembly through each axially segmented nuclide component.
10. A nuclide component analysis device of a spent fuel assembly is characterized by comprising a rod position data module, an AO rod group segmentation module, a fuel consumption proportion module and a fuel consumption calculation module,
the rod position data module is used for respectively acquiring rod position data of each burn-up point of an AO control rod group and a mechanical compensation control rod group in the reactor core in each fuel cycle,
the AO rod set segmentation module is connected with the rod position data module and used for acquiring the calculation segment number N of the AO control rod set according to the rod position data of each burnup point of the AO control rod set in each fuel cycle,
the fuel consumption proportion module is connected with the rod position data module and used for acquiring the maximum fuel consumption depth proportion Z of the mechanical compensation control rod group according to the rod position data of each fuel consumption point of the mechanical compensation control rod group in each fuel cycle k ，
The fuel consumption calculation module is connected with the AO rod group segmentation module and the fuel consumption proportion module and is used for calculating the number of segments N and the maximum fuel consumption depth proportion Z of the mechanical compensation control rod group according to the insertion of the AO control rod group k And performing a burnup calculation on each axial section of the spent fuel assembly to obtain a nuclide component of each axial section of the spent fuel assembly.
11. The apparatus of claim 10, wherein the AO rod set segmentation module comprises an axial segmentation unit, an average insertion depth unit, and a decision unit,
the axial segmentation unit is used for acquiring the axial segmentation number of the spent fuel assembly,
the average insertion depth unit is connected with the rod position data module and is used for obtaining the maximum average insertion depth P of the AO control rod group according to the rod position data of each burn-up point of the AO control rod group in each fuel cycle,
the judging unit is connected with the axial segmenting unit and the average insertion depth unit and used for determining the number N of the calculated segments of the AO control rod group according to the number of the axial segments of the spent fuel assemblies and the maximum average insertion depth P.
12. The apparatus of claim 11, wherein the burnup ratio module includes a maximum insertion depth unit, a corresponding unit, a segment determination unit, a burnup depth ratio unit, and a value selection unit,
the maximum insertion depth unit is used for obtaining the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle according to rod position data of each burn-up point of the mechanical compensation control rod group in each fuel cycle,
the corresponding unit is used for obtaining the corresponding relation between the axial sections and the rod position data of the mechanical compensation control rod group according to the number of the axial sections of the spent fuel assembly,
the segment determining unit is connected with the corresponding unit and used for obtaining the axial segment number corresponding to the maximum insertion depth of the mechanical compensation control rod group in each fuel cycle through the corresponding relation,
the burn-up depth proportion unit is connected with the segmentation determination unit and used for obtaining the burn-up depth proportion Z of the mechanical compensation control rod group in each fuel cycle according to the number of axial segments ik ，
The value selecting unit is connected with the burn-up depth proportion unit and is used for comparing the burn-up depth proportion Z of the mechanical compensation control rod group in each fuel cycle ik Selecting the maximum value, namely the maximum burn-up depth ratio Z of the mechanical compensation control rod set k 。
13. The apparatus of claim 12, wherein the burnup calculation module includes a determination unit and a calculation unit,
the judging unit is connected with the calculating unit and used for judging whether the axial subsection is the front N section of the upper end of the spent fuel assembly:
if yes, a first signal is sent to the computing unit,
if not, judging whether the fuel consumption depth ratio of the axial segmentation is between 100 and Z k In the range: if yes, sending a second signal to the computing unit, if no, sending a third signal to the computing unit,
the calculation unit is used for carrying out fuel consumption calculation on the axial section according to the calculation parameters of the inserted AO control rods when receiving the first signal,
or, upon receipt of the second signal, performing a burnup calculation on the axial segment according to a calculation parameter without insertion of a control rod,
alternatively, upon receipt of the third signal, a fuel consumption calculation is performed on the axial segment in accordance with the calculated parameter for insertion of the mechanical compensation control rods.
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