CN112326286A - Rod-shaped fuel element transient heat release simulation experiment device and method - Google Patents

Rod-shaped fuel element transient heat release simulation experiment device and method Download PDF

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CN112326286A
CN112326286A CN202011166915.1A CN202011166915A CN112326286A CN 112326286 A CN112326286 A CN 112326286A CN 202011166915 A CN202011166915 A CN 202011166915A CN 112326286 A CN112326286 A CN 112326286A
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fuel
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CN112326286B (en
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陈先兵
朱东保
龙成毅
郭洪婧
陈景明
孟海波
刘少有
邵燕
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Wuhan No 2 Ship Design Institute No 719 Research Institute of China Shipbuilding Industry Corp
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Abstract

The invention discloses a bar-shaped fuel element transient heat release simulation experiment device and a method, relating to the field of nuclear reactor thermal hydraulic power and comprising the following steps: s1, constructing a rod-shaped fuel element heat release structure, wherein the rod-shaped fuel element heat release structure comprises pellets, a cladding arranged outside the pellets, and a coolant flow channel positioned outside the cladding, and an air gap is reserved between the pellets and the cladding; s2, calculating time constants of the fuel rods and the electric heating elements, and calculating the real-time thermal power according to the nuclear power of the reactor core; and S3, outputting electric power with corresponding magnitude to the electric heating circular tube in real time by the power supply control system, and carrying out experimental simulation on the transient heat release condition of the rod-shaped element in the reactor by using the electric heating circular tube. The transient heat release simulation experiment device and method for the rod-shaped fuel element solve the problem that the transient heat release process in the fuel rod is difficult to realize in the electric heating process outside the reactor in the prior art.

Description

Rod-shaped fuel element transient heat release simulation experiment device and method
Technical Field
The invention relates to the technical field of nuclear reactor thermal hydraulic power, in particular to a bar-shaped fuel element transient heat release simulation experiment device and method.
Background
The energy in nuclear reactor is mainly from the heat energy generated by fission in nuclear fuel rods, the fuel rods form a nuclear fuel assembly in a certain number and arrangement mode, coolant flows among the fuel rods and brings the heat to a steam generator, and the generated steam pushes a steam turbine to do work to convert the heat energy into mechanical energy. In the design process of the nuclear fuel assembly, experimental study on the flow heat exchange characteristics in the channel of the rod-shaped fuel assembly is needed, but the heat release experiment of the fuel rod cannot be carried out outside the reactor.
The heat release process of the fuel rods in the reactor is generally simulated by adopting an out-of-stack electric heating mode, for example, in the experimental study on convective heat transfer characteristics in a natural circulation heating section of Yangzhou in the prior published literature, the convective heat transfer process in the reactor is simulated by using a stainless steel tube directly heated by alternating current, and the experimental study on natural convective boiling flow instability in a narrow-gap flow passage of Sunzhining simulates the flow boiling instability in the reactor by inserting an electric heating element in a quartz glass tube.
Some technicians establish an electric heating simulation real-time nuclear heat release method in research documents, but the receiving object of electric power is a reactor core model body, and the simulation of a rod-shaped fuel element channel to an electric heating circular tube is not available, and the transient heat release process in a fuel rod cannot be realized in the electric heating process.
These simulated heating experiments conducted outside the reactor are typically only able to simulate steady state heat release processes, and simulation of transient heat release processes lacks an effective means. However, due to the change of the operating conditions and the change of parameters in the reactor, the heat release process in the fuel rod usually shows certain fluctuation and change, and the error influence of the thermal inertia of the round pipe experiment section exists, so that how to realize the simulation method of corresponding transient heat release in the simulation experiment performed outside the reactor is a great technical problem in the field.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a simulation experiment device and a simulation experiment method for transient heat release of a rod-shaped fuel element, which solve the problem that the transient heat release process in a fuel rod is difficult to realize in the electric heating process outside a reactor in the prior art.
In order to achieve the above purposes, the technical scheme adopted by the invention is as follows:
a simulation experiment method for transient heat release of a rod-shaped fuel element comprises the following steps:
s1, constructing a rod-shaped fuel element heat release structure, wherein the rod-shaped fuel element heat release structure comprises pellets, a cladding arranged outside the pellets, and a coolant flow channel positioned outside the cladding, and an air gap is reserved between the pellets and the cladding;
s2, calculating time constants of the fuel rods and the electric heating elements, and calculating the real-time thermal power according to the nuclear power of the reactor core;
and S3, outputting electric power with corresponding magnitude to the electric heating circular tube in real time by the power supply control system, and carrying out experimental simulation on the transient heat release condition of the rod-shaped element in the reactor by using the electric heating circular tube.
On the basis of the above technical solution, the step S2 includes:
establishing an unsteady heat conduction differential equation of the fuel rod; arranging fuel rods in radial symmetry and neglecting heat conduction along the axial direction, and simplifying unsteady heat conduction differential equations of the fuel rods; neglecting the temperature space distribution in the fuel rod, and adopting a centralized parameter model to obtain the relation between the core power of the fuel rod and the thermal power passing through the cladding surface; and establishing a relation between the nuclear power and the thermal power applied to the experimental section by the direct current power supply, and subtracting the time constant of the electric heating circular tube from the time constant of the fuel rod to obtain the time constant of the transient heat release experiment of the fuel rod outside the reactor.
Based on the above technical solution, in step S2, the magnitude of the real-time thermal power is calculated according to the magnitude of the core power according to the following formula:
Figure BDA0002746117370000031
in the formula, QnuclearAnd QthermalRespectively the nuclear power value at the current moment in the core block and the thermal power value obtained at the current moment of the coolant,
Figure BDA0002746117370000034
is the thermal power value at the previous moment, taufuelIs the fuel time constant; Δ t is the time step.
On the basis of the technical scheme, the fuel time constant taufuelCalculated according to the following formula:
Figure BDA0002746117370000032
where ρ isfuelIs the density of the fuel in kg/m3，Cp,fuelIs the specific heat of the fuel, and has the unit of kJ/kg ℃, and h is the convective heat transfer coefficient, and has the unit of kW/m2℃，PhIs the wet cycle of the fuel rod, and has the unit of m, AfuelIs the cross-sectional area of the core block, in m2。
On the basis of the technical scheme, the fuel time constant taufuelCalculated according to the following formula:
Figure BDA0002746117370000033
Qnuclear＝qvAfuelL
Qthermal＝qsPhL
wherein q issIs the heat flow density, qvIs the volumetric heat release rate in kW/m3。
On the basis of the technical scheme, the fuel time constant tau is solvedfuelIn time, a relationship between two adjacent time layers is established, and then the nuclear power Q is solved by using discretenuclear。
On the basis of the above technical solution, in step S2, an unsteady heat conduction differential equation of the fuel rod is established according to the following formula:
Figure BDA0002746117370000041
on the basis of the above technical solution, in step S2, the simplified unsteady heat conduction differential equation for the fuel rod is:
Figure BDA0002746117370000042
the invention also provides a bar-shaped fuel element transient heat release simulation experiment device, which comprises:
the fuel rod comprises pellets and a cladding surrounding and coating the pellets, wherein air gaps with uniform intervals are arranged between the pellets and the cladding;
a coolant flow passage connecting at least two fuel rods forming a closed annular channel structure disposed outside cladding of the fuel rods.
On the basis of the technical scheme, the fuel rods are arranged in a matrix, and the cross section of the coolant flow channel is a rectangle taking the center of the cross section of each fuel rod as a vertex.
Compared with the prior art, the invention has the advantages that:
(1) the transient heat release simulation experiment method for the rod-shaped fuel element establishes a transient heat conduction differential equation in the fuel rod, establishes the relation between the nuclear power and the thermal power by using a fuel time constant, provides a calculation method for calculating the real-time thermal power according to the real-time nuclear power, realizes the simulation of the transient heat release process in the reactor by using electric heating outside the reactor, controls the real-time heating power of the electric heating metal circular tube, corrects the influence of the thermal inertia of the experimental section of the circular tube, and solves the defect that the electric heating outside the reactor can only simulate the steady-state heat release of the fuel rod in the prior art.
(2) According to the transient heat release simulation experiment method for the rod-shaped fuel element, the magnitude of real-time thermal power can be calculated according to real-time nuclear power, and meanwhile, a delay model for transferring heat in the fuel rod to a coolant through pellet-air gap-cladding is established by using a fuel time constant, so that the transient heat release process simulation of the fuel rod is closer to the real situation.
(3) The invention relates to a transient heat release simulation experiment device for a rod-shaped fuel element, which comprises a coolant flow channel which is annularly closed and is used for establishing a transient heat conduction model in fuel. The heat generated by nuclear fission of the fuel pellet is transferred to the outer surface of the cladding through the pellet, the air gap and the cladding in a heat conduction mode and then transferred to the coolant in a convection heat exchange mode, and the simulation of a flowing heat exchange process and a real-time heat release simulation process in a flow channel of the rod-shaped fuel element by using the round tube is realized by only structural arrangement, and the simulation method has the advantages of low cost, good practicability and high precision.
Drawings
FIG. 1 is a schematic structural diagram of a fuel rod used in one embodiment of a transient heat release simulation experiment apparatus for a rod-shaped fuel element according to the present invention;
FIG. 2 is a schematic structural diagram of a flow channel used in an embodiment of the transient heat release simulation experiment apparatus for a rod-shaped fuel element according to the present invention;
FIG. 3 is a schematic structural diagram of an electrically heated metal tube used in an embodiment of the transient heat release simulation experiment apparatus for a rod-shaped fuel element according to the present invention;
FIG. 4 is a flow chart of an embodiment of a rod fuel element transient heat release simulation experiment method of the present invention.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and examples.
Referring to fig. 1 to 3, an embodiment of the present invention provides a simulation experiment apparatus for transient heat release of a rod-shaped fuel element, including:
the fuel rod comprises pellets and a cladding surrounding and coating the pellets, wherein air gaps with uniform intervals are arranged between the pellets and the cladding; a coolant flow passage connecting at least two fuel rods forming a closed annular channel structure disposed outside cladding of the fuel rods.
In a preferred embodiment, the fuel rods are arranged in a matrix, and the coolant flow channel has a rectangular cross section with the center of the cross section of each fuel rod as the apex. Fig. 2 is an arrangement structure of the relative positions of the flow channels and the fuel rods in one embodiment, the fuel rods are arranged in a matrix, a rectangle is constructed with the center of the cross section of each fuel rod at the four vertices of the minimum matrix as the vertex, and the coolant flow channels are arranged with the rectangle as the cross section.
In another aspect, as shown in fig. 4, the present invention also provides a method for conducting a rod fuel element transient heat release simulation experiment using the rod fuel element transient heat release simulation experiment apparatus as described above, which in one embodiment comprises:
s1, constructing a rod-shaped fuel element heat release structure, wherein the rod-shaped fuel element heat release structure comprises pellets, a cladding arranged outside the pellets, and a coolant flow channel positioned outside the cladding, and an air gap is reserved between the pellets and the cladding;
s2, calculating time constants of the fuel rods and the electric heating elements, and calculating the real-time thermal power according to the nuclear power of the reactor core;
and S3, outputting electric power with corresponding magnitude to the electric heating circular tube in real time by the power supply control system, and carrying out experimental simulation on the transient heat release condition of the rod-shaped element in the reactor by using the electric heating circular tube.
In a preferred embodiment, step S2 includes:
establishing an unsteady heat conduction differential equation of the fuel rod; arranging fuel rods in radial symmetry and neglecting heat conduction along the axial direction, and simplifying unsteady heat conduction differential equations of the fuel rods; neglecting the temperature space distribution in the fuel rod, and adopting a centralized parameter model to obtain the relation between the core power of the fuel rod and the thermal power passing through the cladding surface; and establishing a relation between the nuclear power and the thermal power applied to the experimental section by the direct current power supply, and subtracting the time constant of the electric heating circular tube from the time constant of the fuel rod to obtain the time constant of the transient heat release experiment of the fuel rod outside the reactor.
Specifically, in one embodiment, in step S2, the real-time thermal power is calculated according to the core power according to the following formula:
Figure BDA0002746117370000061
in the formula, QnuclearAnd QthermalRespectively the nuclear power value at the current moment in the core block and the thermal power value obtained at the current moment of the coolant,
Figure BDA0002746117370000071
is the thermal power value at the previous moment, taufuelIs the fuel time constant; Δ t is the time step.
Further, the fuel time constant τfuelCalculated according to the following formula:
Figure BDA0002746117370000072
where ρ isfuelIs the density of the fuel in kg/m3，Cp,fuelIs the specific heat of the fuel, and has the unit of kJ/kg ℃, and h is the convective heat transfer coefficient, and has the unit of kW/m2℃，PhIs the wet cycle of the fuel rod, and has the unit of m, AfuelIs the cross-sectional area of the core block, in m2。
Further, the fuel time constant τfuelCalculated according to the following formula:
Figure BDA0002746117370000073
Qnuclear＝qvAfuelL
Qthermal＝qsPhL
wherein q issAs the density of the heat flow,qvis the volumetric heat release rate in kW/m3。
In a preferred embodiment, the fuel time constant τ is solvedfuelIn time, a relationship between two adjacent time layers is established, and then the nuclear power Q is solved by using discretenuclear。
In one embodiment, in step S2, the unsteady heat conduction differential equation of the fuel rod is established according to the following formula:
Figure BDA0002746117370000074
further, in step S2, the simplified unsteady heat conduction differential equation of the fuel rod is:
Figure BDA0002746117370000075
the technical solution of the present invention is explained below with respect to a specific example:
in this example, the technician constructs a rod-shaped fuel element as shown in fig. 1, simplifies the flow path of the coolant into a closed circular channel as shown in fig. 2, and establishes a model of transient heat conduction in the fuel. Heat generated by nuclear fission of the fuel pellets is transferred in the form of heat conduction through the pellets, air gaps, and cladding to the outer cladding surface and then to the coolant in the form of convective heat transfer.
In the experiment of simulating the heat release in the reactor outside the reactor, the coolant flows in the circular heating section, and the physical property and the structure of the circular tube have great difference with the fuel rods in the reactor, so the heat flow density passing through the surface of the fuel rods needs to be calculated according to the transient heat conduction process in the fuel rods, the influence of the experimental section of the circular tube is corrected, and the real-time heat release of the fuel rods is simulated.
Firstly, a mathematical model of the fuel rod heat conduction process is established, and according to the practical situation and the common knowledge in the art, the unsteady heat conduction differential equation of the fuel established in the embodiment is as follows:
Figure BDA0002746117370000081
assuming radial symmetry and neglecting heat conduction in the axial direction, the transient heat conduction differential equation can be simplified as follows:
Figure BDA0002746117370000082
the outer wall surface of the fuel is a third type of boundary condition, and the center of the fuel is a symmetric boundary condition:
Figure BDA0002746117370000083
Figure BDA0002746117370000084
in the formula, ρfuelIs the density of the fuel in kg/m3；Cp,fuelThe specific heat of the fuel is expressed in kJ/kg ℃; t isfuelIs the temperature of the fuel in units of; lambda is the heat conductivity coefficient of the fuel, and the unit is kW/m ℃; r is the distance from the central axis of the fuel rod, and the unit is m; z is the distance along the axial direction of the fuel rod in m; theta is a direction angle; t is time in units of s; q. q.svIs the volumetric heat release rate in kW/m3；TfIs the temperature of the fluid in units of; h is the convective heat transfer coefficient and the unit is kW/m2℃；RSIs the outer radius of the fuel in m.
The spatial distribution of the temperature inside the fuel rod is usually not considered in the experiment of simulating the transient heat release of the fuel rod outside the reactor, and a lumped parameter model is adopted to obtain the relation between the nuclear power inside the fuel rod and the thermal power passing through the cladding surface.
Considering the fuel rod as a whole, equation (2) is further simplified to:
Figure BDA0002746117370000091
heat flux density qs and fuel temperature TfuelThe following relationships exist:
qs＝h(Tfuel-Tcoolant) (6)
neglecting the coolant temperature TcoolantAnd the change of the heat exchange coefficient h, the equation (6) is substituted into the equation (5) to obtain:
Figure BDA0002746117370000092
Figure BDA0002746117370000093
Qnuclear＝qvAfuelL (9)
Qthermal＝qsPhL (10)
in the formula, τfuelIs the fuel time constant in units of s; l is the length of the fuel rod, m; qnuclear and Qthermal are the nuclear power in the pellet and the thermal power obtained by the coolant, kW, respectively.
Equation (7) establishes a relationship between the nuclear power and the thermal power applied to the experimental section by the dc power supply, and the response speed of the thermal power after the nuclear power is changed is related to the fuel time constant, and the larger the fuel time constant is, the slower the response speed of the thermal power is, whereas the smaller the fuel time constant is, the faster the response speed of the thermal power is. And subtracting the time constant of the electric heating circular tube from the test piece constant of the fuel rod to obtain the time constant of the transient heat release experiment of the fuel rod outside the reactor.
Since the kernel power in the equation (7) is an implicit function of time, an analytic solution of the kernel power cannot be obtained, and the analytic solution can be discretely solved, and since a large number of nodes do not need to be divided in space and only the relationship between two adjacent time layers needs to be established in time, the calculation amount is small, the calculation speed is high, and the method is easy to implement in a power control system. The thermal power calculation formula at the current moment is as follows:
Figure BDA0002746117370000101
in the formula, QnuclearAnd QthermalRespectively the nuclear power value at the current moment in the core block and the thermal power value obtained at the current moment of the coolant,
Figure BDA0002746117370000102
the thermal power value at the previous moment is shown as Δ t, which is the time step.
When the experiment for simulating the heat release of the fuel rods outside the reactor is carried out, firstly, the time constants of the fuel rods and the electric heating elements are calculated, according to the sizes of the reactor core and the power, the real-time thermal power is calculated according to the size of the nuclear power of the reactor core through an equation (11), and then the electric power with the corresponding size is output to the electric heating circular tube through the power control system in real time, so that the experiment simulation of the transient heat release of the rod-shaped elements in the reactor by using the electric heating circular tube outside the reactor is realized. The electric heating element is arranged as shown in figure 3, and is formed by clamping two electrodes on a metal round tube, wherein the electrodes are connected with a high-power supply, and the metal round tube is heated by a power supply control system.
The present invention is not limited to the above-described embodiments, and it will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the principle of the present invention, and such modifications and improvements are also considered to be within the scope of the present invention. Those not described in detail in this specification are within the skill of the art.

Claims (10)

1. A simulation experiment method for transient heat release of a rod-shaped fuel element is characterized by comprising the following steps:
s1, constructing a rod-shaped fuel element heat release structure, wherein the rod-shaped fuel element heat release structure comprises pellets, a cladding arranged outside the pellets, and a coolant flow channel positioned outside the cladding, and an air gap is reserved between the pellets and the cladding;
s2, calculating time constants of the fuel rods and the electric heating elements, and calculating the real-time thermal power according to the nuclear power of the reactor core;
and S3, outputting electric power with corresponding magnitude to the electric heating circular tube in real time by the power supply control system, and carrying out experimental simulation on the transient heat release condition of the rod-shaped element in the reactor by using the electric heating circular tube.
2. The rod fuel element transient heat release simulation experiment method of claim 1, wherein the step S2 includes:
establishing an unsteady heat conduction differential equation of the fuel rod;
arranging fuel rods in radial symmetry and neglecting heat conduction along the axial direction, and simplifying unsteady heat conduction differential equations of the fuel rods;
neglecting the temperature space distribution in the fuel rod, and adopting a centralized parameter model to obtain the relation between the core power of the fuel rod and the thermal power passing through the cladding surface;
and establishing a relation between the nuclear power and the thermal power applied to the experimental section by the direct current power supply, and subtracting the time constant of the electric heating circular tube from the time constant of the fuel rod to obtain the time constant of the transient heat release experiment of the fuel rod outside the reactor.
3. The rod-shaped fuel element transient heat release simulation experiment method as set forth in claim 1, wherein in the step S2, the real-time thermal power is calculated according to the core nuclear power according to the following formula:
Figure FDA0002746117360000021
in the formula, QnuclearAnd QthermalRespectively the nuclear power value at the current moment in the core block and the thermal power value obtained at the current moment of the coolant,
Figure FDA0002746117360000024
is the thermal power value at the previous moment, taufuelIs the fuel time constant; Δ t is the time step.
4. A rod fuel element transient heat release simulation test method as defined in claim 3, wherein said fuel time constant τ isfuelCalculated according to the following formula:
Figure FDA0002746117360000022
where ρ isfuelIs the density of the fuel in kg/m3，Cp,fuelIs the specific heat of the fuel, and has the unit of kJ/kg ℃, and h is the convective heat transfer coefficient, and has the unit of kW/m2℃，PhIs the wet cycle of the fuel rod, and has the unit of m, AfuelIs the cross-sectional area of the core block, in m2。
5. The rod fuel element transient heat release simulation test method of claim 4, wherein the fuel time constant τ isfuelCalculated according to the following formula:
Figure FDA0002746117360000023
Qnuclear＝qvAfuelL
Qthermal＝qsPhL
wherein q issIs the heat flow density, qvIs the volumetric heat release rate in kW/m3。
6. The rod fuel element transient heat release simulation test method of claim 5, wherein:
in solving for fuel time constant τfuelIn time, a relationship between two adjacent time layers is established, and then the nuclear power Q is solved by using discretenuclear。
7. The rod-shaped fuel element transient heat release simulation experiment method of claim 1, wherein in step S2, a fuel rod unsteady state heat conduction differential equation is established according to the following formula:
Figure FDA0002746117360000031
8. the rod-shaped fuel element transient heat release simulation experiment method of claim 7, wherein in the step S2, the simplified fuel rod unsteady state heat conduction differential equation is:
Figure FDA0002746117360000032
9. a simulation experiment device for transient heat release of a rod-shaped fuel element is characterized by comprising:
the fuel rod comprises pellets and a cladding surrounding and coating the pellets, wherein air gaps with uniform intervals are arranged between the pellets and the cladding;
a coolant flow passage connecting at least two fuel rods forming a closed annular channel structure disposed outside cladding of the fuel rods.
10. The rod fuel element transient heat release simulation test apparatus of claim 9, wherein:
the fuel rods are arranged in a matrix, and the cross section of the coolant flow channel is a rectangle taking the center of the cross section of each fuel rod as a vertex.
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CN112967579B (en) * 2021-03-25 2022-05-03 深圳大学 An experimental setup for studying annular fuel thermal imbalance
CN115331851A (en) * 2022-08-24 2022-11-11 上海核工程研究设计院有限公司 Nuclear fuel element for power transient test, test device and method

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