CN116401500A - Calculation method for nuclide concentration of long-distance concealed pipe inside and outside water body in periodic discharge mode - Google Patents

Calculation method for nuclide concentration of long-distance concealed pipe inside and outside water body in periodic discharge mode Download PDF

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CN116401500A
CN116401500A CN202310359013.7A CN202310359013A CN116401500A CN 116401500 A CN116401500 A CN 116401500A CN 202310359013 A CN202310359013 A CN 202310359013A CN 116401500 A CN116401500 A CN 116401500A
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nuclide
concentration
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concealed pipe
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CN116401500B (en
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曾利
王晓亮
赵懿珺
张海文
纪平
胥密
陈小莉
梁洪华
段亚飞
秦晓
左庆宁
白晓平
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China Institute of Water Resources and Hydropower Research
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Abstract

The invention relates to a calculation method of the nuclide concentration of a long-distance concealed pipe inner and outer water body in a periodic discharge mode, which comprises the following steps: judging whether the hydraulic dispersion type process belongs to a long-time hydraulic dispersion type process; solving flux of the nuclide discharged at the inlet of the concealed pipe; expanding the periodic nuclide flux into a fourier series form; calculating the distribution of the nuclide concentration caused by constant component items of the nuclide flux; calculating the distribution of the nuclide concentration caused by the cosine component of the nuclide flux; calculating the distribution of the nuclide concentration caused by the sine series component of the nuclide flux; obtaining the concentration distribution of nuclides in the long-distance concealed pipe by linear superposition; obtaining the dynamic change of the nuclide concentration and flux of the outlet of the long-distance concealed pipe; and the concentration distribution of the nuclide in the sea area around the outlet of the long-distance concealed pipe. The invention provides a quantitative calculation method for the nuclide concentration of the water body inside and outside the long-distance concealed pipe in an accurate forecast period emission mode, and provides scientific basis for planning, demonstration and design of a spent fuel post-treatment plant and water environment safety evaluation.

Description

Calculation method for nuclide concentration of long-distance concealed pipe inside and outside water body in periodic discharge mode
Technical Field
The invention relates to a calculation method of the nuclide concentration of a long-distance buried pipe in and out of water body in a periodic discharge mode, which is a hydraulic engineering design calculation method and is a calculation method applied to the drainage engineering of a nuclear power spent fuel post-treatment plant.
Background
In order to ensure the safety of nuclear power, radioactive nuclear waste is generated in the operation process of the nuclear power plant, and the nuclear waste is properly treated by a spent fuel post-treatment plant. In the normal operation process of the coastal spent fuel post-treatment plant, nuclides such as tritium and the like can be discharged to the environmental water body. In order to reduce the influence of the nuclides discharged by the coastal post-treatment plant on the environmental water body, the nuclides are required to be conveyed to a proper water area of the open sea for discharging through long-distance concealed pipes. In order to fully utilize the diluting and mixing characteristics of the sea tides, the nuclide discharge mode can adopt periodic discharge, namely multiple rows under the condition of better hydrodynamic conditions and fewer rows under the condition of poorer hydrodynamic conditions. In order to accurately grasp the ecological environmental influence of the sea area of the nuclides discharged by the spent fuel post-treatment plant, the nuclide concentration of the water body inside and outside the long-distance concealed pipe needs to be simulated and forecasted, and the calculation method of the nuclide concentration of the water body inside and outside the long-distance concealed pipe in a periodic discharge mode is an important technical support for developing the works by related departments, and has important significance for planning, designing and running of the spent fuel post-treatment plant.
The nuclide concentration transport of the water body inside and outside the long-distance concealed pipe involves two processes: the nuclear transport inside the concealed pipe and the nuclear transport in the sea area around the outlet of the concealed pipe. The hydrodynamic conditions inside and outside the concealed pipe have obvious difference: the flow state in the concealed pipe is pressurized flow, the flow state in the sea area around the concealed pipe is pressureless flow, and the concentration distribution of nuclides in the water body inside and outside the concealed pipe is difficult to calculate simultaneously based on a single pressurized flow model and a pressureless flow model. The existing calculation method is mainly aimed at continuous constant source discharge or short-distance hidden pipe periodic discharge, and does not consider the change of nuclide concentration along the flowing direction (longitudinal direction) of the hidden pipe, namely, the hidden pipe outlet concentration is assumed to be equal to the hidden pipe inlet concentration. For the periodic discharge of long-distance concealed pipes, the nuclide concentration is transported in the concealed pipes for a long time, and the outlet concentration and the inlet concentration of the concealed pipes are obviously different from each other: (1) The concentration of the outlet of the concealed pipe has a delayed response relative to the concentration of the inlet, i.e. the nuclide of the inlet of the concealed pipe needs to take several hours or even more to reach the outlet of the concealed pipe; (2) The concentration of nuclides in the concealed pipe is unevenly distributed in the water flow direction under the influence of water entrainment and dilution diffusion and in a periodical discharge mode, and the concentration of nuclides at the outlet of the concealed pipe is obviously different from the concentration at the inlet of the concealed pipe. Therefore, the existing method can not accurately reflect the delayed response of the nuclide concentration of the long-distance concealed pipe outlet and the entrainment and dilution diffusion effects of the concealed pipe water flow under the periodic discharge mode, thereby affecting the accuracy of simulating and forecasting the surrounding sea area nuclide concentration field by taking the nuclide flux of the concealed pipe outlet as a source item. Therefore, the exploration of the calculation method capable of accurately forecasting the nuclide concentration of the water body inside and outside the long-distance concealed pipe in the periodic emission mode has very important significance for planning, demonstration and design of the spent fuel post-treatment plant and water environment safety assessment.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention provides a calculation method for the nuclide concentration of a long-distance concealed pipe inner and outer water body in a periodic discharge mode. The method utilizes an analytic method to calculate the nuclide concentration distribution in the pressured concealed pipe, obtains the variation process of the nuclide concentration and flux of the outlet of the concealed pipe, and simulates and calculates the sea area nuclide concentration field, thereby obtaining the nuclide concentration distribution of the water body inside and outside the concealed pipe.
The purpose of the invention is realized in the following way: a calculation method of the nuclide concentration of a long-distance concealed pipe inner and outer water body in a periodic discharge mode comprises the following steps:
step 1, judging whether the process belongs to a long-time hydraulic dispersion type process: whether the nuclide transport process in the concealed pipe belongs to a long-time hydraulic dispersion type process, namely: whether the ratio of the length L of the concealed pipe to the average flow velocity U of the section of the concealed pipe is far greater than the square of the hydraulic diameter W of the concealed pipe and the longitudinal diffusion coefficient D of nuclide in the flow of the concealed pipe ξ Ratio of; if yes, entering the next step, and if not, ending the calculation;
step 2, calculating flux q (t) of the nuclide discharged at the inlet of the concealed pipe: acquiring a periodic discharge flow parameter: discharge flow rate Q in And a time-varying emission profile C in (t):q(t)=Q in C in (t);
Step 3, expanding the periodical nuclide flux into a Fourier series form: expanding the periodic nuclear flux q (t) discharged at the inlet of the concealed pipe into a fourier series:
Figure BDA0004164344830000021
wherein a is 0 、a m 、b m Is the Fourier expansion coefficient; t is time; t is the nuclide emission period; m is the number of items of the Fourier series expansion of the nuclide flux, is a positive integer, and M is the maximum number of items of the Fourier series approximate expansion;
step 4, calculating the distribution of the nuclide concentration caused by constant component items of the nuclide flux: calculating constant term components of the flux of the inlet of the concealed conduit nuclide
Figure BDA0004164344830000022
The resulting emission concentration profile:
Figure BDA0004164344830000023
wherein:
Figure BDA0004164344830000024
λ n to satisfy the positive root of the following transcendental equation:
Figure BDA0004164344830000025
in the above formula: ζ is the pipe coordinate, ζ=0 represents the pipe inlet position; n is a positive integer;
lambda was calculated using the following algorithm n
i) Calculation of
Figure BDA0004164344830000031
Break point coordinates ζ of right item r
Figure BDA0004164344830000032
ii) calculation of
Figure BDA0004164344830000033
Break point coordinates u of left term r
Figure BDA0004164344830000034
iii) Calculating the initial coordinate xi of the interval where the 1 st positive root is s
Figure BDA0004164344830000035
Figure BDA0004164344830000036
Wherein: floor () is a rounding function;
iv) calculating
Figure BDA0004164344830000037
The interval in which the positive root is located:
s +iu rs +(i+1)u r ],i=0,2,4,…I
wherein: zeta type toy r The break point coordinates for the right item calculated in step i); u (u) r The first break point coordinates of the left term calculated for step ii); zeta type toy s The starting coordinates of the interval in which the 1 st positive root calculated in step iii) is located; n is n r Numbering the intervals in which the first positive root calculated for step iii) is located; i is an even number; i is the maximum value taken by I, and the larger I represents the higher number of the taken series items;
v) applying conventional numerical algorithm to the pairs
Figure BDA0004164344830000038
Solving each positive root interval to obtain lambda n
Step 5, calculating the distribution of the nuclide concentration caused by the cosine component of the nuclide flux: computing cosine series expansion term components
Figure BDA0004164344830000039
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000041
step 6, calculating the distribution of the nuclide concentration caused by the sine series component of the nuclide flux: calculating sinusoidal series expansion term components
Figure BDA0004164344830000042
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000043
step 7, obtaining the concentration distribution of the nuclide in the long-distance concealed pipe by linear superposition: by superimposing C 0 (ξ,t)、
Figure BDA0004164344830000044
Calculating the concentration profile in the dark tube caused by the nuclide flux q:
Figure BDA0004164344830000045
step 8, obtaining the dynamic change of the nuclide concentration and flux of the long-distance concealed pipe outlet: calculating nuclide flux q at outlet of concealed pipe out Is a periodic variation of (a):
q out (t)=QC(L,t);
step 9, the concentration distribution of the nuclides in the sea area around the long-distance concealed pipe outlet: adding long-distance dark tube outlet flow and nuclide concentration as input parameters into a source item of a general pollutant transport model, establishing a nuclide concentration field model of a water area around the dark tube outlet, and calculating a nuclide concentration field of a sea area around the outlet;
the nuclide transport model boundary conditions are set as follows:
water level-flow rate boundary conditions: a free sliding boundary condition is adopted at the bank boundary, and a tide level boundary condition is adopted at the open sea boundary;
nuclide concentration boundary conditions: a zero flux boundary condition is adopted at the bank boundary, and a zero gradient boundary condition is adopted at the open sea boundary;
water level-flow rate initial conditions: the initial water level is set to be the average sea level height, and the initial flow rate is set to be 0;
nuclide concentration initial conditions: zero concentration initial conditions were set.
The invention has the advantages and beneficial effects that: according to the invention, complex periodic nuclide discharge flux at an inlet of the concealed pipe is expanded into flux in a Fourier series form, the nuclide concentration distribution in long-distance pressurized concealed pipe flowing under the action of single Fourier series flux is calculated by an analytic method, and then the nuclide concentration distribution in the concealed pipe is obtained based on a linear superposition principle, so that the change process of the nuclide concentration and flux at an outlet of the concealed pipe is obtained; and taking the outlet periodic nuclide concentration and the flow of the concealed pipe obtained by the analysis method as source items of a conventional sea area nuclide concentration transport model, and simulating and calculating a sea area nuclide concentration field so as to obtain the nuclide concentration distribution of the water body inside and outside the long-distance concealed pipe. The invention provides a quantitative calculation method for the nuclide concentration of the water body inside and outside the long-distance concealed pipe in an accurate forecast period emission mode, and provides scientific basis for planning, demonstration and design of a spent fuel post-treatment plant and water environment safety evaluation.
Drawings
The invention is further described below with reference to the drawings and examples.
FIG. 1 is a flow chart of a method according to an embodiment of the invention;
FIG. 2 shows the calculation results of the concentration distribution of the core element in the concealed pipe at different moments in the application example of the embodiment of the invention;
FIG. 3 is a graph showing the calculation of the concentration of the nuclide at the outlet of the concealed conduit with time in the application example of the embodiment of the present invention;
FIG. 4 is a graph showing the calculation of the flux of the nuclear species at the outlet of the blind pipe over time in an example of application of the embodiment of the present invention;
FIG. 5 is a contour of the instantaneous distribution of the concentration of a nuclear species around the outlet of a dark tube in an example application of an embodiment of the present invention;
FIG. 6 is a tidal level verification of a model in an example application of an embodiment of the present invention;
FIG. 7 is a graph showing the fixed point flow rate verification of a model in an example of application of an embodiment of the present invention;
FIG. 8 is a graph showing the verification of the direction of the fixed-point flow velocity of the model in the application example of the embodiment of the present invention.
Detailed Description
Embodiment one:
the embodiment is a calculation method of the nuclide concentration of the inner and outer water bodies of a long-distance concealed pipe in a periodic discharge mode, and the flow of the calculation method is shown in a figure 1.
According to the integral thought of the calculation method, the thought of combining an analysis algorithm with a numerical algorithm is adopted, complex periodic nuclide discharge flux at an inlet of the concealed pipe is unfolded to flux in a Fourier series form, the analysis method is used for calculating nuclide concentration distribution in long-distance pressurized concealed pipe flowing under the action of single Fourier series flux, then the nuclide concentration distribution in the concealed pipe is obtained based on a linear superposition principle, and further the change process of nuclide concentration and flux at an outlet of the concealed pipe is obtained; and taking the outlet periodic nuclide concentration and the flow of the concealed pipe obtained by the analysis method as source items of a conventional sea area nuclide concentration transport model, and simulating and calculating a sea area nuclide concentration field so as to obtain the nuclide concentration distribution of the water body inside and outside the long-distance concealed pipe.
The specific steps of the method in this embodiment are as follows:
step 1, judging whether the process belongs to a long-time hydraulic dispersion type process: whether the nuclide transport process in the concealed pipe belongs to a long-time hydraulic dispersion type process, namely: whether the ratio of the length L of the concealed pipe to the average flow velocity U of the section of the concealed pipe is far greater than the square of the hydraulic diameter W of the concealed pipe and the longitudinal diffusion coefficient D of nuclide in the flow of the concealed pipe ξ Ratio of; if yes, go to the next step, if not, end the calculation.
The step is to judge first
Figure BDA0004164344830000061
If so, the nuclide concentration in the concealed pipe is mainly distributed unevenly along the longitudinal direction in a long-time hydraulic dispersion process, and the nuclide concentration distribution of the water body inside and outside the long-distance concealed pipe can be calculated by adopting the calculation method.
Wherein the length L of the concealed pipe, the average flow velocity U of the section of the concealed pipe and the hydraulic diameter W of the concealed pipe are approximately determined in the initial stage of the design of the concealed pipe and are known values, and the longitudinal diffusion coefficient D of nuclide in the flow of the concealed pipe ξ Also in the case of a determination of the cross-sectional dimensions of the concealed conduit, the average flow velocity of the concealed conduit.
The following describes the calculation method of each step described in this embodiment with a certain project as an application example:
the engineering parameters are as follows: l=1000 m, u=0.05 m/s, D ξ =50m 2 /s,W=2m
Figure BDA0004164344830000062
2×10 4 >>0.08
The two differ by 6 orders of magnitude and can therefore be calculated using the method described in this example. Typically the two are several orders of magnitude different, i.e. considered to be much larger.
Step 2, calculating flux q (t) of the nuclide discharged at the inlet of the concealed pipe: acquiring a periodic discharge flow parameter: discharge flow rate Q in And a time-varying emission profile C in (t):q(t)=Q in C in (t)。
The application examples are as follows: periodic discharge flow parameters: q (Q) in =0.2m 3 /s,
Figure BDA0004164344830000063
T=12 hours=4.32×10 4 s. The nuclide concentration unit is set to be 1 per cubic meter, i.e. 1/m 3 . Thus (S)>
Figure BDA0004164344830000064
Step 3, expanding the periodical nuclide flux into a Fourier series form: expanding the periodic nuclear flux q (t) discharged at the inlet of the concealed pipe into a fourier series:
Figure BDA0004164344830000065
wherein a is 0 、a m 、b m Is the Fourier expansion coefficient; t is time; t is the nuclide emission period; m is the number of terms of the Fourier series expansion of the nuclide flux, is a positive integer, and M is the maximum number of terms of the Fourier series approximate expansion. In practical application, finite term (M term) series summation is selected according to the precision required by the user.
The application examples are as follows:
a 0 =2(1/s)
a m =0(1/s)
Figure BDA0004164344830000071
step 4, calculating the distribution of the nuclide concentration caused by constant component items of the nuclide flux: calculating constant term components of the flux of the inlet of the concealed conduit nuclide
Figure BDA0004164344830000072
The resulting emission concentration profile:
Figure BDA0004164344830000073
wherein:
Figure BDA0004164344830000074
λ n to satisfy the positive root of the following transcendental equation:
Figure BDA0004164344830000075
in the above formula: ζ is the pipe coordinate, ζ=0 represents the pipe inlet position; n is a positive integer and is selected according to the required precision.
Lambda was calculated using the following algorithm n
i) Calculating the coordinate xi of the break point of the right item of the formula (4) r
Figure BDA0004164344830000076
ii) calculating the break point coordinates u of the left term of (4) r
Figure BDA0004164344830000081
iii) Calculating the initial coordinate xi of the interval where the 1 st positive root is s
Figure BDA0004164344830000082
Figure BDA0004164344830000083
Wherein: floor () is a rounding function.
iv) calculating the interval of the positive root of (4)
s +iu rs +(i+1)u r ],i=0,2,4,…I (9)
Wherein: zeta type toy r The break point coordinates for the right item calculated in step i); u (u) r The first break point coordinates of the left term calculated for step ii); zeta type toy s The starting coordinates of the interval in which the 1 st positive root calculated in step iii) is located; n is n r Numbering the intervals in which the first positive root calculated for step iii) is located; i is an even number; i is the maximum value taken by I, and the larger I represents the higher number of the taken series items;
v) solving each positive root interval of (4) by adopting a conventional numerical algorithm to obtain lambda n
The application examples are as follows:
calculating an entry flux constant term component
Figure BDA0004164344830000084
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000085
wherein:
Figure BDA0004164344830000086
λ n for positive root, the following transcendental equation is satisfied:
Figure BDA0004164344830000091
the application example here selects a 5-term series for summation.
Calculating lambda n
i) Calculating the coordinate xi of the break point of the right item of the formula (4) r
Figure BDA0004164344830000092
ii) calculating the break point coordinates u of the left term of (4) r
Figure BDA0004164344830000093
iii) Calculating the initial coordinate xi of the interval where the 1 st positive feature root is located s
Figure BDA0004164344830000094
ξ s =0
iv) calculating the interval of the characteristic root of (4):
[iu r ,(i+1)u r ],i=0,2,4,…8
wherein: i is an even number;
v) solving the characteristic root interval of the formula (4) in the formula (9) by adopting a conventional numerical algorithm to obtain:
λ 1 =0.001570794109、λ 2 =0.004712367024、λ 3 =0.007853920200、λ 4 =0.01099545364、λ 5 =0.01413696734。
step 5, calculating the distribution of the nuclide concentration caused by the cosine component of the nuclide flux: computing cosine series expansion term components
Figure BDA0004164344830000095
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000101
in practical application, finite term (N term) series summation is selected according to the precision required by the user.
The application examples are as follows: computing cosine series expansion term components
Figure BDA0004164344830000102
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000103
step 6, calculating the distribution of the nuclide concentration caused by the sine series component of the nuclide flux: calculating sinusoidal series expansion term components
Figure BDA0004164344830000104
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000111
in practical application, finite term (N term) series summation is selected according to the precision required by the user.
The application examples are as follows: calculating sinusoidal series expansion term components
Figure BDA0004164344830000112
The resulting dark tube emission concentration profile:
Figure BDA0004164344830000113
step 7, obtaining the concentration distribution of the nuclide in the long-distance concealed pipe in a periodic discharge mode by linear superposition: by superimposing C 0 (ξ,t)、
Figure BDA0004164344830000121
Calculating the concentration profile in the dark tube caused by the nuclide flux q:
Figure BDA0004164344830000122
the nuclide concentration C (xi, t) in the long-distance concealed pipe can be calculated by C 0 (ξ,t)、
Figure BDA0004164344830000123
The superposition was demonstrated as follows:
the nuclide concentration transport control equation, boundary conditions and initial conditions in the long-distance blind duct channel are as follows:
control equation:
Figure BDA0004164344830000124
boundary conditions:
Figure BDA0004164344830000125
initial conditions:
C(ξ,0)=0 (15)
wherein: c is the concentration of the species in the flow of the concealed conduit, ζ is the concealed conduit position coordinate, ζ=0 is the concealed conduit inlet position coordinate, and ζ=l is the concealed conduit outlet position coordinate.
Due to C 0 (ξ,t)、
Figure BDA0004164344830000126
The solution problem is respectively satisfied:
Figure BDA0004164344830000127
Figure BDA0004164344830000128
C 0 (ξ,0)=0 (18)
Figure BDA0004164344830000129
Figure BDA00041643448300001210
Figure BDA00041643448300001211
Figure BDA00041643448300001212
Figure BDA0004164344830000131
Figure BDA0004164344830000132
from the superposition of the linear equations, it is known that:
Figure BDA0004164344830000133
Figure BDA0004164344830000134
Figure BDA0004164344830000135
therefore, the solution of the formula (12) satisfies the control equation (13), the boundary condition (14) and the initial condition (15), namely the solution of the nuclide concentration in the long-distance blind duct channel.
The application examples are as follows: linear superposition calculation:
Figure BDA0004164344830000136
fig. 2 shows the concentration profiles of the nuclides in the dark tubes at different moments (6 hours, 12 hours, 18 hours, 24 hours) of the application example.
Step 8, obtaining the dynamic change of the nuclide concentration and flux of the long-distance concealed pipe outlet in a periodic emission mode: calculating nuclide flux q at outlet of concealed pipe out Is a periodic variation of (a):
q out (t)=QC(L,t)。 (28)
the application examples are as follows: calculating the nuclide concentration and flux q at the outlet of the concealed pipe out Is a periodic variation of (a):
C e (t)=C(L,t)
q out (t)=QC(L,t)=0.2C(L,t)。
figure 3 shows the calculated results of the concentration of the outlet nuclide of the blind pipe over time. Figure 4 shows the calculation of the flux of the nuclear species at the outlet of the blind pipe over time. Table 1 shows the flow and concentration of the dark tube outlet nuclide over time for 1 discharge cycle. Table 2 gives the variation of the outlet nuclide flux of the blind pipe over time for 1 discharge cycle.
TABLE 1 variation of outlet nuclide flow and concentration of the blind tube (1 discharge cycle)
Time(s) Flow (m) 3 /s) Concentration (1/m) 3 ) Time(s) Flow (m) 3 /s) Concentration (1/m) 3 )
0 0.2 0 18000 0.2 12.85697
600 0.2 0.195966 18600 0.2 12.87678
1200 0.2 0.641684 19200 0.2 12.8661
1800 0.2 1.272187 19800 0.2 12.8258
2400 0.2 1.964003 20400 0.2 12.7569
3000 0.2 2.671111 21000 0.2 12.66059
3600 0.2 3.373521 21600 0.2 12.53823
4200 0.2 4.061833 22200 0.2 12.39129
4800 0.2 4.731502 22800 0.2 12.22144
5400 0.2 5.380271 23400 0.2 12.03043
6000 0.2 6.006934 24000 0.2 11.82016
6600 0.2 6.610725 24600 0.2 11.59264
7200 0.2 7.19103 25200 0.2 11.34998
7800 0.2 7.747247 25800 0.2 11.09438
8400 0.2 8.278734 26400 0.2 10.82809
9000 0.2 8.784796 27000 0.2 10.55344
9600 0.2 9.264686 27600 0.2 10.27278
10200 0.2 9.717624 28200 0.2 9.988517
10800 0.2 10.14282 28800 0.2 9.703027
11400 0.2 10.53948 29400 0.2 9.418702
12000 0.2 10.90684 30000 0.2 9.1379
12600 0.2 11.24419 30600 0.2 8.86294
13200 0.2 11.55089 31200 0.2 8.596079
13800 0.2 11.82636 31800 0.2 8.339503
14400 0.2 12.07014 32400 0.2 8.095305
15000 0.2 12.28187 33000 0.2 7.865474
15600 0.2 12.46134 33600 0.2 7.65188
16200 0.2 12.60845 34200 0.2 7.456258
16800 0.2 12.72326 34800 0.2 7.280199
17400 0.2 12.80598 35400 0.2 7.125138
TABLE 2 variation of the outlet nuclide flux of the concealed conduit over time (1 discharge cycle)
Time(s) Flux (1/s) Time(s) Flux (1/s)
0 0 18000 2.571395
600 0.039193 18600 2.575356
1200 0.128337 19200 2.573221
1800 0.254437 19800 2.56516
2400 0.392801 20400 2.55138
3000 0.534222 21000 2.532119
3600 0.674704 21600 2.507645
4200 0.812367 22200 2.478259
4800 0.9463 22800 2.444287
5400 1.076054 23400 2.406085
6000 1.201387 24000 2.364032
6600 1.322145 24600 2.318528
7200 1.438206 25200 2.269997
7800 1.549449 25800 2.218876
8400 1.655747 26400 2.165618
9000 1.756959 27000 2.110688
9600 1.852937 27600 2.054557
10200 1.943525 28200 1.997703
10800 2.028563 28800 1.940605
11400 2.107895 29400 1.88374
12000 2.181368 30000 1.82758
12600 2.248839 30600 1.772588
13200 2.310177 31200 1.719216
13800 2.365272 31800 1.667901
14400 2.414028 32400 1.619061
15000 2.456375 33000 1.573095
15600 2.492268 33600 1.530376
16200 2.52169 34200 1.491252
16800 2.544652 34800 1.45604
17400 2.561195 35400 1.425028
Step 9, the concentration distribution of the nuclides in the sea area around the long-distance concealed pipe outlet: and adding the long-distance hidden pipe outlet flow and the nuclide concentration as input parameters into a source item of a general pollutant transportation model, establishing a nuclide concentration field model of a water area around the hidden pipe outlet, and calculating a nuclide concentration field of a sea area around the outlet.
The nuclide transport model boundary conditions are set as follows:
water level-flow rate boundary conditions: the bank boundary adopts a free sliding boundary condition, and the open sea boundary adopts a tide level boundary condition.
Nuclide concentration boundary conditions: a zero flux boundary condition is adopted at the bank boundary, and a zero gradient boundary condition is adopted at the open sea boundary.
Water level-flow rate initial conditions: the initial water level was set to mean sea level height and the initial flow rate was set to 0.
Nuclide concentration initial conditions: zero concentration initial conditions were set.
The application examples are as follows: and selecting the MIKE21 model as a peripheral nuclide transport model of the outlet, inputting the long-distance concealed pipe outlet position (506274,3808682), the outlet nuclide flow and concentration (13 calculation results) as source items into the MIKE21 model, and establishing a nuclide concentration field model of a water area around the concealed pipe outlet. The calculation is performed by taking a certain coastal area of southeast China as an example. In the MIKE21 model, the boundary conditions, initial conditions are set as follows:
boundary condition setting:
water level-flow rate boundary conditions: the bank boundary adopts a free sliding boundary condition, and the open sea boundary is given a periodic tide level process.
Nuclide concentration boundary conditions: the shore boundary adopts a zero flux boundary condition, and the open sea boundary adopts a zero gradient boundary condition.
Initial condition setting:
water level: giving an average sea level height;
flow rate: 0m/s;
nuclide concentration: zero initial concentration is used;
FIG. 5 shows the contour of the concentration distribution of the nuclear species around the outlet of the dark tube in the periodic discharge mode. Model tidal level, flow rate, flow direction validation results are shown in fig. 6-8.
Finally, it should be noted that the above only illustrates the technical solution of the present invention, and not limiting, and although the present invention has been described in detail with reference to the preferred arrangement, it will be understood by those skilled in the art that the technical solution of the present invention (such as the form of the concealed conduit, the application of various formulas or models, the sequence of steps, etc.) may be modified or replaced equivalently, without departing from the spirit and scope of the technical solution of the present invention.

Claims (1)

1. A calculation method of the nuclide concentration of a long-distance concealed pipe inner and outer water body in a periodic discharge mode is characterized by comprising the following steps:
step 1, judging whether the process belongs to a long-time hydraulic dispersion type process: whether the nuclide transport process in the concealed pipe belongs to a long-time hydraulic dispersion type process, namely: whether the ratio of the length L of the concealed pipe to the average flow velocity U of the section of the concealed pipe is far greater than the square of the hydraulic diameter W of the concealed pipe and the longitudinal diffusion coefficient D of nuclide in the flow of the concealed pipe ξ Ratio of; if yes, entering the next step, and if not, ending the calculation;
step 2, calculating flux q (t) of the nuclide discharged at the inlet of the concealed pipe: acquisition weekPhase discharge flow parameters: discharge flow rate Q in And a time-varying emission profile C in (t):q(t)=Q in C in (t);
Step 3, expanding the periodical nuclide flux into a Fourier series form: expanding the periodic nuclear flux q (t) discharged at the inlet of the concealed pipe into a fourier series:
Figure FDA0004164344820000011
wherein a is 0 、a m 、b m Is the Fourier expansion coefficient; t is time; t is the nuclide emission period; m is the number of items of the Fourier series expansion of the nuclide flux, is a positive integer, and M is the maximum number of items of the Fourier series approximate expansion;
step 4, calculating the distribution of the nuclide concentration caused by constant component items of the nuclide flux: calculating constant term components of the flux of the inlet of the concealed conduit nuclide
Figure FDA0004164344820000012
The resulting emission concentration profile:
Figure FDA0004164344820000013
wherein:
Figure FDA0004164344820000014
λ n to satisfy the positive root of the following transcendental equation:
Figure FDA0004164344820000015
in the above formula: ζ is the pipe coordinate, ζ=0 represents the pipe inlet position; n is a positive integer, and is selected according to the required precision;
lambda was calculated using the following algorithm n
i) Calculation of
Figure FDA0004164344820000021
Break point coordinates ζ of right item r
Figure FDA0004164344820000022
ii) calculation of
Figure FDA0004164344820000023
Break point coordinates u of left term r
Figure FDA0004164344820000024
iii) Calculating the initial coordinate xi of the interval where the 1 st positive root is s
Figure FDA0004164344820000025
Figure FDA0004164344820000026
Wherein: floor () is a rounding function;
iv) calculating
Figure FDA0004164344820000027
The interval in which the positive root is located:
s +iu rs +(i+1)u r ],i=0,2,4,…I
wherein: zeta type toy r The break point coordinates for the right item calculated in step i); u (u) r The first break point coordinates of the left term calculated for step ii); zeta type toy s The starting coordinates of the interval in which the 1 st positive root calculated in step iii) is located; n is n r Numbering the intervals in which the first positive root calculated for step iii) is located; i is an even number; i is the maximum value taken by I, and the larger I represents the higher number of the taken series items;
v) applying conventional numerical algorithm to the pairs
Figure FDA0004164344820000028
Solving each positive root interval to obtain lambda n
Step 5, calculating the distribution of the nuclide concentration caused by the cosine component of the nuclide flux: computing cosine series expansion term components
Figure FDA0004164344820000029
The resulting dark tube emission concentration profile:
Figure FDA0004164344820000031
step 6, calculating the distribution of the nuclide concentration caused by the sine series component of the nuclide flux: calculating sinusoidal series expansion term components
Figure FDA0004164344820000032
The resulting dark tube emission concentration profile:
Figure FDA0004164344820000033
step 7, obtaining the concentration distribution of the nuclide in the long-distance concealed pipe by linear superposition: by superimposing C 0 (ξ,t)、
Figure FDA0004164344820000034
Calculating the concentration profile in the dark tube caused by the nuclide flux q:
Figure FDA0004164344820000035
step 8, obtaining the dynamic change of the nuclide concentration and flux of the long-distance concealed pipe outlet: calculating nuclide flux q at outlet of concealed pipe out Is a periodic variation of (a):
q out (t)=QC(L,t);
step 9, the concentration distribution of the nuclides in the sea area around the long-distance concealed pipe outlet: adding long-distance dark tube outlet flow and nuclide concentration as input parameters into a source item of a general pollutant transport model, establishing a nuclide concentration field model of a water area around the dark tube outlet, and calculating a nuclide concentration field of a sea area around the outlet;
the nuclide transport model boundary conditions are set as follows:
water level-flow rate boundary conditions: a free sliding boundary condition is adopted at the bank boundary, and a tide level boundary condition is adopted at the open sea boundary;
nuclide concentration boundary conditions: a zero flux boundary condition is adopted at the bank boundary, and a zero gradient boundary condition is adopted at the open sea boundary;
water level-flow rate initial conditions: the initial water level is set to be the average sea level height, and the initial flow rate is set to be 0;
nuclide concentration initial conditions: zero concentration initial conditions were set.
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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20040009455A1 (en) * 2002-07-09 2004-01-15 Ren-Tai Chiang Monte carlo criticality-mode systems and methods for computing neutron and gamma fluence in a nuclear reactor
CN102867121A (en) * 2012-09-06 2013-01-09 中国能源建设集团广东省电力设计研究院 Method for analyzing influence of plume of cooling tower on nuclear waste gas concentration distribution on nuclear island
CN107133412A (en) * 2017-05-15 2017-09-05 中国水利水电科学研究院 The quick calculation method that multicomponent radionuclide concentration is forecast in a kind of river course
CN113282867A (en) * 2020-02-19 2021-08-20 清华大学 Method, apparatus, device and medium for predicting radiation dose rate of radionuclide
CN114386229A (en) * 2021-11-30 2022-04-22 中国辐射防护研究院 Radionuclide coastal real-time migration diffusion calculation method and system

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20040009455A1 (en) * 2002-07-09 2004-01-15 Ren-Tai Chiang Monte carlo criticality-mode systems and methods for computing neutron and gamma fluence in a nuclear reactor
CN102867121A (en) * 2012-09-06 2013-01-09 中国能源建设集团广东省电力设计研究院 Method for analyzing influence of plume of cooling tower on nuclear waste gas concentration distribution on nuclear island
CN107133412A (en) * 2017-05-15 2017-09-05 中国水利水电科学研究院 The quick calculation method that multicomponent radionuclide concentration is forecast in a kind of river course
CN113282867A (en) * 2020-02-19 2021-08-20 清华大学 Method, apparatus, device and medium for predicting radiation dose rate of radionuclide
CN114386229A (en) * 2021-11-30 2022-04-22 中国辐射防护研究院 Radionuclide coastal real-time migration diffusion calculation method and system

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
PENGHUI YAO 等: "A Method of Monitoring Partial Discharge in Switchgear Based on Ozone Concentration", IEEE TRANSACTIONS ON PLASMA SCIENCE, vol. 47, no. 1, pages 654 - 660, XP011695633, DOI: 10.1109/TPS.2018.2876412 *
王平 等: "湿地流动中污染物弥散过程的解析研究", 第二十九届全国水动力学研讨会, pages 1434 - 1441 *

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