CN114547996B - Nuclear power plant two-loop system and calculation method for nuclide accumulated activity of equipment - Google Patents

Nuclear power plant two-loop system and calculation method for nuclide accumulated activity of equipment Download PDF

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CN114547996B
CN114547996B CN202210185564.1A CN202210185564A CN114547996B CN 114547996 B CN114547996 B CN 114547996B CN 202210185564 A CN202210185564 A CN 202210185564A CN 114547996 B CN114547996 B CN 114547996B
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夏庚磊
鲜磊
彭敏俊
赵强
孙觊琳
王航
张博文
王晨阳
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Abstract

The invention provides a nuclear power plant two-loop system and a calculation method of nuclide cumulative activity of equipment, which comprises the step of obtaining the mass C of a nuclide i released from a nuclear power plant one loop to a two loop in unit time i And the state, the two-loop fluid network nodes are divided, then the position nodes of the leaked air are obtained according to the two-loop fluid network, the leakage coefficient of the radionuclide i is calculated, the deposition efficiency of the radionuclide i in each device is calculated, the accumulated mass balance equation of the radionuclide i in each device is established, and finally the accumulated specific activity conversion of the device is carried out by considering the gas-liquid distribution problem of the suspended nuclide.

Description

Nuclear power plant two-loop system and calculation method for nuclide accumulated activity of equipment
Technical Field
The invention relates to the technical field of nuclear reactor engineering, in particular to a nuclear power plant two-loop system and a calculation method of nuclear species accumulated activity of equipment.
Background
The steam generator is a core component for heat transmission in the reactor system, is also an important component of a pressure boundary of a loop system of the reactor, and plays an important role in isolating the radioactivity of the loop. Because the two sides of the heat exchange tube of the steam generator have larger temperature difference and pressure difference, larger mechanical stress and thermal stress exist, and meanwhile, the high-speed flowing of the fluid in the first loop and the fluid in the second loop can generate vibration and corrosion effects, the heat transfer tube is easy to break, so that the coolant in the first loop leaks to the second loop, radioactive substances can migrate to a system in the second loop and gradually diffuse into the environment along with the lapse of time, and permanent damage is caused to the natural environment and workers in a plant area;
reliability and safety of a nuclear power system are always the highest targets pursued by nuclear power station construction, and radioactive safety is the most concerned problem in reactor accident safety analysis. In order to deal with serious consequences caused by steam generator heat transfer pipe rupture accidents possibly occurring under extremely severe conditions, the migration characteristics of radioactive substances after the accidents occur need to be studied in advance, the accumulation and leakage amount of the radioactive substances are determined, so that the accident process and the radioactive consequences can be evaluated in detail, and reference is provided for making an emergency response plan and taking accident relieving measures in time.
Disclosure of Invention
In view of the above problems, the present invention is directed to a nuclear power plant secondary loop system and a method for calculating nuclide cumulative activity of equipment, which can well calculate the radioactive substance cumulative activity in the nuclear power plant secondary loop equipment after a steam generator heat transfer tube rupture accident occurs, and solve the problem that the migration and accumulation of nuclides between the secondary loop equipment cannot be well calculated in the prior art.
In order to realize the purpose of the invention, the invention is realized by the following technical scheme: a nuclear power plant secondary loop system and a nuclear power plant nuclide cumulative activity calculation method comprises the following steps:
the method comprises the following steps: determining the species of the radionuclide i released by the rupture of the heat transfer pipe of the steam generator, and acquiring the mass C of the radionuclide i released from one loop to the second loop of the nuclear power plant in unit time i And a status;
step two: dividing two-loop fluid network nodes according to the type of two-loop equipment, the inlet and outlet flow of each branch and actual physical parameters;
step three: according to the second loop fluid network in the step two, the inlet and outlet flow of each node of the equipment fluid network, the pressure in each node and the internal mass are obtained by combining a thermal model, the position node of the leaked air is obtained, and the leakage coefficient of the radionuclide i is calculated;
step four: calculating the deposition efficiency of the nuclide i in each device;
step five: establishing an accumulated mass balance equation of the radionuclide i of each device according to the flow network flow parameters of the two-loop device and the physical property parameters of the nuclide i;
step six: and 4, converting the cumulative specific activity of the equipment by considering the gas-liquid distribution problem of the suspended nuclide.
The further improvement lies in that: in the first step, the state and the quality of the real-time release of the radionuclide i are reasonably and simply obtained through an SGTR release source item provided by a nuclear power plant and by combining with the properties of a flow network.
The further improvement lies in that: in the second step, an unstructured node division method is adopted, and the number of unknowns needed by the calculation equation is reduced on the basis of meeting the actual physical functions of all devices.
The further improvement is that: in the third step, the method for calculating the leakage coefficient of the radionuclide i comprises the following steps:
Q＝Ve*(ΔP/Patm)*(60/ΔT)
Figure GDA0003875453820000031
in the formula, Q is the leakage amount, ve is the equivalent internal volume, Δ P is the internal and external pressure difference, patm is the atmospheric pressure, and M is the gas mass in the node at this time.
The further improvement lies in that: in the fourth step, the calculation method for calculating the deposition efficiency of the nuclide i in each device comprises the following steps:
η 1 ＝1-exp(-πDLV + u * /Q)
Figure GDA0003875453820000032
Figure GDA0003875453820000033
Figure GDA0003875453820000034
Figure GDA0003875453820000035
Figure GDA0003875453820000036
K3＝αη 1 +(1-α)η 2
in the formula eta 1 The turbulent flow deposition efficiency of the equipment; eta 2 Efficiency of thermophoretic deposition of the device; k3 is the overall deposition efficiency of the apparatus; alpha is a weighting coefficient; d is the diameter of the equipment; l is the length of the equipment; v + Dimensionless speed; v. of * Is the friction speed; sc is the Schmidt number; v is the kinematic viscosity coefficient;
Figure GDA0003875453820000041
is dimensionless gravity; t is t w Is the shear stress of the pipeline wall; rho a Is the air density; k th Is the thermophoresis coefficient; t is a unit of c Is the inlet temperature, T w Is the wall temperature.
The further improvement is that: in the fifth step, the cumulative mass balance equation of the radionuclide i of each device is as follows:
A 1 X 1 ＝B 1
in the formula (I), the compound is shown in the specification,
Figure GDA0003875453820000042
C i1 ，C i2 …C in respectively the mass of the nuclide i of each upstream and downstream equipment, alpha 11 ，α 12 …α m Is the coefficient of the mass balance equation of the upstream and downstream equipment, beta 1 ，β 2 …β n Is a constant term of the mass balance equation of the upstream and downstream equipment.
The further improvement lies in that: in the sixth step, the conversion method of the cumulative specific activity of the equipment comprises the following steps:
Figure GDA0003875453820000043
in the formula, Q i Is the cumulative activity of the device for the species i, and M refers to the species distributed by the species i.
The further improvement lies in that: in the sixth step, the mass of the accumulated radioactive substance of the device at the time T is calculated by combining the nuclide accumulation balance equation of the two-loop device with an appropriate time constant, and the calculated accumulated mass of the radioactive substance at the time T is also used for calculating the accumulated activity of the device after the next time constant.
The invention has the beneficial effects that: the nuclear power plant two-loop system and the calculation method of the nuclide accumulated activity of the equipment are suitable for building an accumulated activity model of each equipment of the whole two-loop equipment flow network, a balance equation is divided according to the state of the nuclide substance, the influences of deposition, decay and leakage are fully considered, gas-liquid distribution in nodes is carried out on suspended radioactive substances by means of the quantity of the radioactive substances and physical property parameters in the nodes, and therefore specific activity is conveniently calculated.
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FIG. 1 is a flowchart illustrating a first step of the present invention.
Fig. 2 is an overall flowchart of a second embodiment of the present invention.
Detailed Description
In order to further understand the present invention, the following detailed description will be made with reference to the following examples, which are only used for explaining the present invention and are not to be construed as limiting the scope of the present invention.
Example one
Referring to fig. 1, the embodiment provides a nuclear power plant secondary loop system and a method for calculating nuclide cumulative activity of equipment, including the following steps:
the method comprises the following steps: determining the species of the radionuclide i released by the rupture of the heat transfer pipe of the steam generator, and acquiring the mass C of the radionuclide i released from one loop to the second loop of the nuclear power plant in unit time i And the state, the state and the quality of the real-time release of the radionuclide i are reasonably and simply obtained by an SGTR release source item provided by a nuclear power plant and the combination of the properties of the flow network;
step two: dividing two-loop fluid network nodes according to the type of two-loop equipment, the inlet and outlet flow of each branch and actual physical parameters, and reducing the number of unknowns required by a calculation equation on the basis of meeting the actual physical functions of each equipment by adopting an unstructured node division method;
step three: according to the two-loop fluid network in the step two, the inlet and outlet flow, the pressure in each node and the internal mass of each node of the equipment fluid network are obtained by combining a thermal model, the position node of the leakage air is obtained, the leakage coefficient of the radionuclide i is calculated, and the method for calculating the leakage coefficient of the radionuclide i comprises the following steps:
Q＝Ve*(ΔP/Patm)*(60/ΔT)
Figure GDA0003875453820000061
in the formula, Q is leakage quantity, ve is equivalent internal volume, delta P is internal and external pressure difference, patm is atmospheric pressure, and M is gas mass in the node at the moment;
step four: calculating the deposition efficiency of the nuclide i in each device, wherein the calculation method for calculating the deposition efficiency of the nuclide i in each device comprises the following steps:
η 1 ＝1-exp(-πDLV + u * /Q)
Figure GDA0003875453820000062
Figure GDA0003875453820000063
Figure GDA0003875453820000064
Figure GDA0003875453820000065
Figure GDA0003875453820000066
K3＝αη 1 +(1-α)η 2
in the formula eta 1 Turbulent flow deposition efficiency of the equipment; eta 2 Efficiency of thermophoretic deposition of the device; k3 is the total deposition efficiency of the equipment; alpha is a weighting coefficient; d is the diameter of the equipment; l is the length of the equipment; v + Is a dimensionless speed; v. of * Is the friction speed; sc is the Schmidt number; v is the kinematic viscosity coefficient;
Figure GDA0003875453820000067
is dimensionless gravity; t is t w Is the shear stress of the pipeline wall; ρ is a unit of a gradient a Is the air density; k is th Is the thermophoresis coefficient; t is c Is the inlet temperature, T w Is the wall temperature;
step five: establishing an accumulated mass balance equation of the radioactive nuclide i of each device according to the flow network flow parameter of the two-loop device and the physical property parameter of the nuclide i, wherein the method for establishing the accumulated mass balance equation of the radioactive nuclide i of each device is as follows:
when the nuclide is a soluble radionuclide or an inert gas, the way to calculate the cumulative mass of the device radionuclide i is:
Figure GDA0003875453820000071
when the nuclide is an inert gas or a soluble radionuclide, the way to calculate the cumulative mass of the device radionuclide i is:
Figure GDA0003875453820000072
in the formula (I), the compound is shown in the specification,
Figure GDA0003875453820000073
is the mass change rate of inert gas or soluble radionuclide i, R is the source term of radionuclide i, M 1 Total mass flow, Q, contained at the last moment in time on a node flowing into the plant c Mass flow into the plant from the last node, C i10 Mass of the nuclide i in the previous node, λ being the decay constant, γ, of the nuclide i j The ratio of the decay of the nuclide j to the nuclide i, K1 is the leakage fraction of the nuclide i, K2 is the inflow fraction of the nuclide i to other loops, and K3 is the deposition efficiency of the nuclide i;
the main difference of the mass balance equation of the two nuclides i is whether the influence of deposition is considered, and the mass balance equation is simplified by using a finite difference and dispersion method, so that the time dispersion can be obtained:
Figure GDA0003875453820000074
and converting mass balance equations of soluble gas and inert gas to obtain: alpha (alpha) ("alpha") 11 C i1 +α 12 C i10 ＝β 1
Wherein alpha is 11 ＝1，
Figure GDA0003875453820000081
Figure GDA0003875453820000082
Wherein, C i1 (t 0 ) The method comprises the following steps of (1) listing the mass balance equation of a complete soluble radioactive substance i according to the mass of the radioactive substance i in a node at the last moment and the mass balance equation of the radioactive substance i in each upstream and downstream device in a simultaneous manner, wherein the accumulated mass balance equation of the radioactive substance i in each device is as follows:
A 1 X 1 ＝B 1
in the formula (I), the compound is shown in the specification,
Figure GDA0003875453820000083
C i1 ，C i2 …C in respectively the mass of the nuclide i of each upstream and downstream equipment, alpha 11 ，α 12 …α nn Is the coefficient of the mass balance equation of the upstream and downstream equipment, beta 1 ，β 2 …β n Is a constant term of the mass balance equation of the upstream and downstream equipment.
Step six: the method for converting the cumulative specific activity of the equipment by considering the gas-liquid distribution problem of the suspended nuclide comprises the following steps:
Figure GDA0003875453820000084
in the formula, Q i The device is used for accumulating activity of nuclide i, M refers to a substance distributed by the nuclide i, inert gas refers to total gas mass in the device, soluble radioactive substance refers to total liquid mass in the device, and the gas-liquid distribution problem needs to be considered for suspended radionuclides.
Example two
Referring to fig. 2, the embodiment provides a nuclear power plant secondary loop system and a method for calculating nuclide cumulative activity of equipment, including the following steps:
the method comprises the following steps: obtaining the mass C of the nuclide i released from one loop to the second loop of the nuclear power plant in unit time based on the release source item of the SGTR accident i And the state of the nuclide i in the step refers to whether the nuclide is distributed in a gas state or a liquid state, and as the calculation method needs to consider the deposition process and the leakage process of the nuclide i, the state of the nuclide source item needs to be determined so as to simplify the deposition and leakage equation, the state and the quality of the real-time release of the radionuclide i can be reasonably obtained through releasing the source item by SGTR provided by a nuclear power plant and combining the properties of a flow network so as to facilitate subsequent calculation;
step two: dividing two-loop fluid network nodes according to the type of two-loop equipment and the inlet and outlet flow of each branch, wherein in the step, due to the fact that the number and the type of the two-loop fluid network equipment are large and complex, huge workload is needed for the structural division of the whole two-loop, and then an unstructured node division method is adopted, on the basis of meeting the actual physical function of each equipment, the number of unknowns needed by a calculation equation is reduced, and the solving difficulty is reduced;
step three: according to the position nodes of the leakage air of the two-loop equipment fluid network, the leakage coefficient of the radionuclide i is calculated, in the step, the concentration of the radionuclide i in the leakage is assumed to be unchanged in the nodes, the leakage coefficient of the radionuclide i is calculated through a pressure balance equation, the method simplifies the problem of gas-liquid entrainment, avoids complex entrainment calculation, and calculates the leakage coefficient of the radionuclide i by acquiring the position nodes of the leakage air of the two-loop equipment fluid network and combining the pressure inside and outside the nodes and the concentration of the node radionuclide i;
step four: calculating the deposition efficiency of the nuclide i in each device according to the turbulence deposition model and the thermophoresis deposition model, and determining the weight coefficient of the deposition efficiency according to the type of each device in the step;
step five: establishing an accumulated mass balance equation of each equipment radionuclide i according to flow parameters of a two-loop equipment flow network and physical property parameters of nuclides i, in the step, acquiring the inlet and outlet flow of a certain equipment flow network of the two loops through a thermal model or experimental data, calculating the deposition coefficient of the nuclides in the equipment through a deposition efficiency model, calculating the leakage coefficient of the nuclides i, acquiring decay constants of the nuclides i and the fraction and decay constants of other nuclides j decaying into i through experimental data, calculating the changed mass of the nuclides i in the equipment, establishing the mass balance equation, and using different mass balance equations according to the calculated states of the radionuclides;
step six: and in the step, the mass of the accumulated radioactive substances of the equipment at the moment T is calculated by combining a two-loop equipment nuclide accumulation balance equation with a proper time constant, the calculated accumulated mass of the radioactive substances is also used for calculating the accumulated activity of the equipment after the next time constant, and the specific activity of the equipment needs to be converted according to the accumulated mass of the equipment radionuclide i according to the state of the selected nuclide.
The foregoing illustrates and describes the principles, general features, and advantages of the present invention. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are described in the specification and illustrated only to illustrate the principle of the present invention, but that various changes and modifications may be made therein without departing from the spirit and scope of the present invention, which fall within the scope of the invention as claimed. The scope of the invention is defined by the appended claims and equivalents thereof.

Claims (8)

1. A nuclear power plant secondary loop system and a nuclear power plant nuclide cumulative activity calculation method are characterized in that: the method comprises the following steps:
the method comprises the following steps: determining the species of the radionuclide i released by the rupture of the heat transfer pipe of the steam generator, and acquiring the mass C of the radionuclide i released from one loop to the second loop of the nuclear power plant in unit time i And a status;
step two: dividing two-loop fluid network nodes according to the type of two-loop equipment, the inlet and outlet flow of each branch and actual physical parameters;
step three: according to the second loop fluid network in the second step, the inlet and outlet flow, the pressure in each node and the internal mass of each node of the equipment fluid network are obtained by combining a thermal model, the position node of leaked air is obtained, and the leakage coefficient of the radionuclide i is calculated;
step four: calculating the deposition efficiency of the nuclide i in each device;
step five: establishing an accumulated mass balance equation of the radionuclide i of each device according to the flow network flow parameters of the two-loop device and the physical property parameters of the nuclide i;
step six: and 4, converting the cumulative specific activity of the equipment by considering the gas-liquid distribution problem of the suspended nuclide.
2. The nuclear power plant secondary loop system and equipment nuclide cumulative activity calculation method as claimed in claim 1, wherein: in the first step, the state and the quality of the real-time release of the radionuclide i are reasonably and simply obtained through SGTR release source items provided by a nuclear power plant and by combining the properties of a flow network.
3. The nuclear power plant secondary loop system and equipment nuclide cumulative activity calculation method as claimed in claim 1, wherein: in the second step, an unstructured node division method is adopted, and the number of unknowns needed by the calculation equation is reduced on the basis of meeting the actual physical functions of each device.
4. The method for calculating nuclide cumulative activity of a nuclear power plant two-loop system and equipment as defined in claim 1, wherein: in the third step, the method for calculating the leakage coefficient of the radionuclide i comprises the following steps:
Q＝Ve*(ΔP/Patm)*(60/ΔT)
Figure FDA0003875453810000021
in the formula, Q is the leakage amount, ve is the equivalent internal volume, Δ P is the internal and external pressure difference, patm is the atmospheric pressure, and M is the gas mass in the node at this time.
5. The method for calculating nuclide cumulative activity of a nuclear power plant two-loop system and equipment as defined in claim 1, wherein: in the fourth step, the calculation method for calculating the deposition efficiency of the nuclide i in each device comprises the following steps:
η 1 ＝1-exp(-πDLV + u * /Q)
Figure FDA0003875453810000026
Figure FDA0003875453810000022
Figure FDA0003875453810000023
Figure FDA0003875453810000024
Figure FDA0003875453810000025
K3＝αη 1 +(1-α)η 2
in the formula eta 1 The turbulent flow deposition efficiency of the equipment; eta 2 Efficiency of thermophoretic deposition of the device; k3 is the overall deposition efficiency of the apparatus; alpha is a weighting coefficient; d is the diameter of the equipment; l is the length of the equipment; v + Is a dimensionless speed; v. of * Is the friction speed; sc is the Schmidt number; v is the kinematic viscosity coefficient;
Figure FDA0003875453810000031
is dimensionless gravity; t is t w Is a pipe wallShear stress of the face; rho a Is the air density; k th Is the thermophoresis coefficient; t is c Is the inlet temperature, T w Is the wall temperature.
6. The nuclear power plant secondary loop system and equipment nuclide cumulative activity calculation method as claimed in claim 1, wherein: in the fifth step, the cumulative mass balance equation of the radionuclide i of each device is as follows:
A 1 X 1 ＝B 1
in the formula (I), the compound is shown in the specification,
Figure FDA0003875453810000032
C i1 ，C i2 …C in respectively the mass of the nuclide i of each upstream and downstream equipment, alpha 11 ，α 12 …α nn Is the coefficient of the mass balance equation of the upstream and downstream equipment, beta 1 ，β 2 …β n Is a constant term of the mass balance equation of the upstream and downstream equipment.
7. The method for calculating nuclide cumulative activity of a nuclear power plant two-loop system and equipment as defined in claim 1, wherein: in the sixth step, the method for converting the cumulative specific activity of the equipment comprises the following steps:
Figure FDA0003875453810000033
in the formula, Q i Is the cumulative activity of the device for the species i, and M refers to the species to which the species i is distributed.
8. The nuclear power plant secondary loop system and equipment nuclide cumulative activity calculation method as claimed in claim 1, wherein: in the sixth step, the accumulated mass of the radioactive substances of the device at the time T is calculated by combining the nuclide accumulation balance equation of the two-loop device with the time constant, and the accumulated mass of the radioactive substances calculated at the time T is also used for calculating the accumulated activity of the device after the next time constant.
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