CN110531635B - Fast reactor main pump flow channel modeling calculation method based on virtual valve - Google Patents
Fast reactor main pump flow channel modeling calculation method based on virtual valve Download PDFInfo
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Abstract
The invention discloses a fast reactor main pump flow channel modeling calculation method based on a virtual valve, belonging to the technical field of electric pile three-dimensional numerical simulation. Reasonably simplifying a reactor container and reactor internals based on the pool type sodium-cooled fast reactor, and establishing a three-dimensional pool type fast reactor model; the fast reactor in-reactor three-dimensional thermotechnical fluid transient calculation under various working conditions can be carried out by using a model, the transient working conditions of the in-reactor flow process can be accurately simulated by changing the attributes of all surfaces of the communication coupling module between the main pump and the pressure pipe and carrying out partial simple change on the surface attributes of the communication coupling module of the main pump of the loop, and the fast reactor loop accident system analysis and the in-reactor fluid three-dimensional thermotechnical transient calculation under various working conditions comprise normal operation, predicted operation events and accident working conditions. The invention greatly reduces the workload of modeling and calculation. The calculation of a plurality of working conditions can be completed by using one set of grid files, and support and basis are provided for fast reactor design and safety analysis.
Description
Technical Field
The invention belongs to the technical field of fast reactor three-dimensional numerical simulation, and particularly relates to a fast reactor main pump flow channel modeling calculation method based on a virtual valve. In particular to a method for analyzing a fast reactor primary circuit accident system and calculating three-dimensional thermal transient state of fluid in a reactor under various working conditions, which comprises normal operation, predicted operation events and accident working conditions.
Background
Fast reactors are an important direction for fourth generation reactors, which can consume nuclear waste produced by thermal neutron reactors, utilize non-fissile nuclides that are widely present in nature and cannot be utilized by thermal neutron reactors, and produce heat energy. Taking a pool type sodium-cooled fast reactor as an example, the system comprises a primary sodium loop, a secondary sodium loop and a sodium-water (steam) heat exchanger, and a reactor core, a primary loop coolant pump, an outlet pipeline of the primary loop coolant pump and an intermediate heat exchanger are arranged in a sodium pool to form an integrated structure. Liquid metal sodium is used as a primary loop coolant and a secondary loop heat carrier. The stack body is integrally arranged. The upper part of the main container is an argon cavity which isolates a loop of sodium and the external atmosphere. A loop has two parallel loops. Each loop has a main circulation pump and two intermediate heat exchangers. The in-pile structure is very complex, and the structural size difference of different in-pile components is huge, thereby providing great challenge for numerical simulation calculation.
Many one-dimensional and two-dimensional system software analyses are performed on a loop system in the reactor at home and abroad, for example, a FASYS program developed by the Chinese atomic energy institute for accident analysis of the pool type sodium-cooled fast reactor, THPCS and THACS developed by the Western traffic university, and some foreign accident analysis software such as SSC-L, SSC-K, SIMMER and the like, and one-dimensional or two-dimensional system analysis results are obtained. However, the hydraulic fluid characteristics in the pool type fast reactor have obvious three-dimensional characteristics, and detailed three-dimensional transient characteristic simulation is required. At present, the three-dimensional calculation of the fast reactor at home and abroad is mostly a local single part, such as Zhang daong and the like, which are used for researching the influence of different arrangement modes of tube bundles in an intermediate heat exchanger on the internal temperature and the temperature distribution of a flow field, Faruk and the like, which are used for researching the influence of different positions and different shapes of the internal blockage of a box of components on the temperature field and the flow field in the box, and also used for carrying out three-dimensional and two-dimensional calculation on a main container cooling system of the pool type fast reactor, and Bredan and the like establish a simple model aiming at a loop of the fast reactor to carry out thermal stratification phenomenon analysis in the loop. For the coupling simulation of the full stack of the pool type fast reactor, A.Toti et al uses RELAP5 and FLUENT to carry out three-dimensional calculation under the water loss transient state aiming at the study of the MYRRHA of the stack, U.Parthasarhy et al uses a method of combining commercial software and two-loop one-dimensional software to calculate the effect of a waste heat discharge system of a PHENIX stack, and permissive force et al carries out modeling and transient calculation on a cold and hot sodium pool of CEFR, but the model is relatively simplified more, and the flow characteristic of the fluid in the stack under various working conditions cannot be accurately simulated. At present, the precedent of carrying out full-stack and detailed three-dimensional transient numerical simulation on the fast reactor is lacked at home and abroad.
The invention provides a fast reactor main pump flow channel modeling calculation method based on a virtual valve, taking a pool type sodium-cooled fast reactor as an example, through different treatments to boundary conditions under different accidents, three-dimensional thermal transient calculation of the pool type sodium-cooled fast reactor under various accident conditions can be carried out by establishing a set of grids, and the workload of grid modification and modeling can be greatly reduced. For example, in the event of a water loss accident, two primary circuit main pumps can normally operate, but the reactor core is stopped at the moment, and the flow of the primary circuit main pump is changed to match the change in the reactor, wherein the inlet of the main pump is the boundary condition of the fixed flow inlet for the model. When a pump shaft clamping accident occurs, the boundary condition of one main pump is not changed, and the fluid thermal parameters passing through the other main pump are no longer known boundary conditions and can be obtained by calculation. When a power failure accident of a whole plant occurs, two main pumps of a loop are idled, after the idleness is finished, an inlet and an outlet are not arranged in a reactor, natural circulation in the reactor is established, fluid thermal parameters passing through the two pumps are unknown, and the two pumps cannot be used as boundary conditions for calculation. The research result can provide support and basis for the design of the fast reactor.
Disclosure of Invention
The invention aims to provide a fast reactor main pump flow channel modeling calculation method based on a virtual valve, which is characterized in that a loop in a fast reactor container is a pool type sodium-cooled fast reactor loop formed by connecting two main pumps 7, a communication coupling module 13, a pressure pipe 5, a grid plate header 3 and a reactor core 2, and is a closed system, the b surface and the d surface of the communication coupling module 13 at two sides are set as internal surfaces, and the a surface and the c surface are set as solid surfaces; the surface e is a channel for the fluid to enter the pump from the cold pool; the calculation of the loop three-dimensional thermal fluid transient state comprises the following steps:
step 1, respectively arranging a communication coupling module for boundary condition conversion at the joint of two main pumps and a pressure pipe of a loop, connecting the communication coupling module and an integral fast reactor model through an interface in a fluent, and changing a flow inlet or closing the flow inlet of the fast reactor model by adjusting the surface type of the interface in the fluent, thereby simplifying a grid model and enabling one set of grid model to be used for calculation of multiple working conditions;
step 3, determining physical parameters of the sodium fluid, wherein the physical parameters of the sodium are density, viscosity and specific heat capacity of liquid sodium input before calculation, and then calculating to obtain three-dimensional thermotechnical hydraulic parameters of the fluid at each position in the reactor, including temperature, speed and pressure of the fluid; and physical parameters of the materials of the components: the density, specific heat capacity and viscosity of sodium are adopted in fluent to change along with temperature; the body cold sources of the intermediate heat exchanger IHX and the waste heat discharging heat exchanger DHX and the body heat source of the reactor core are controlled by writing a Users-defined function program carried in the fluent, so that the power of each component of the pool type sodium-cooled fast reactor under different working conditions is controlled to change along with time.
Boundary conditions of the fast reactor model are as follows: an inlet fluid is fed at the inlet of the pressure tube and a pressure outlet is fed above the pressure tube, inside the pump.
When the steady state is calculated, the sodium flow of a primary circuit in the reactor can be simulated only by artificially setting an inlet and an outlet, wherein the inlet is arranged at the impeller outlet of a main pump, namely the surface c of a model where the main pump is connected with a pressure pipe, and the outlet is arranged at the surface a of the impeller inlet of the main pump in an actual model and is arranged as a pressure outlet, so that the flow of the primary circuit is balanced; the boundary conditions for different conditions are changed by changing the various face properties of the transition section and the control of inlet flow and temperature by the circumscribed line udf under different accident conditions.
The method has the advantages that the three-dimensional thermodynamic fluid transient calculation in the fast reactor under various working conditions can be carried out by using one model, and the three-dimensional calculation under the working conditions can be realized by partially and simply changing the surface properties of the coupling module for communicating between the main pump and the pressure pipe and greatly reducing the workload of modeling and calculation. Different boundary conditions can be given under different working conditions, calculation of multiple working conditions can be completed by using one set of grid file, and support and basis are provided for fast reactor design and safety analysis.
Drawings
FIG. 1 is a schematic diagram of a built pool type fast reactor model.
Fig. 2 is a schematic view of a circuit coolant flow path.
FIG. 3 illustrates the internal fluid flow at the main pump and pressure tube intercommunicating coupling module, wherein (a) the transitional intercommunicating coupling module is set to strategy 1; (b) a transition communication coupling module sets a strategy 2;
Detailed Description
The invention provides a fast reactor main pump flow channel modeling calculation method based on a virtual valve, which is described below by combining with the accompanying drawings.
Fig. 1 is a schematic diagram of a pool type fast reactor model. The established pool type fast reactor comprises a central measuring column 1, a reactor core 2, a grid plate header 3, a main container 4, a pressure pipe 5, an in-reactor support 6, two primary loop main pumps 7, an overflow window 8, a biological shielding column 9, an intermediate heat exchanger 10, an out-of-reactor biological shielding column 11, a reactor core shield 12, a communication coupling module 13, a reactor core melting collector and a sodium extruder; in the three-dimensional pool type fast reactor model, after entering the grid plate header 3 through the main pump 7 and the pressure pipe 5, the fluid is distributed in flow rate, most of the fluid enters the reactor core 2 to be heated, flows out of the reactor core 2, enters the hot pool area through the overflow windows 8 on the biological shielding columns 9, enters the intermediate heat exchanger 10 to be cooled, then is sent back to the cold pool, and then is driven into the reactor core 2 by the main pump 7, and the flowing route of the fluid is shown by an arrow in fig. 1.
Fig. 2 is a schematic view of a primary coolant flow path. The primary circuit in the fast reactor container is a pool type sodium-cooled fast reactor primary circuit formed by connecting two main pumps 7, a communication coupling module 13, a pressure pipe 5, a grid plate header 3 and a reactor core 2, is a closed system, and sets the b surface and the d surface of the communication coupling module 13 at two sides as the inner surface and sets the a surface and the c surface as the solid surfaces; the surface e is a channel for the fluid to enter the pump from the cold pool; the calculation of the loop three-dimensional thermal fluid transient state comprises the following steps:
step 1, respectively arranging a communicating coupling module 13 for boundary condition conversion at the joint of two main pumps and a pressure pipe of a loop, connecting the communicating coupling module 13 and an integral fast reactor model in a fluent through an interface (as shown in figures 1 and 2), setting a surface b and a surface d of the communicating coupling module 13 at two sides into inner surfaces and setting a surface a and a surface c into entity surfaces by adjusting the surface type of the interface in the fluent; the flow inlet of the fast reactor model is changed or closed, so that the grid model is simplified, and a set of grid model can be used for calculation under various working conditions;
Step 3, determining physical parameters of the sodium fluid, wherein the physical parameters of the sodium are density, viscosity and specific heat capacity of liquid sodium input before calculation, and then calculating to obtain three-dimensional thermotechnical hydraulic parameters of the fluid at each position in the reactor, including temperature, speed and pressure of the fluid; and physical parameters of the materials of the components: the density, specific heat capacity and viscosity of sodium are adopted in fluent to change along with temperature; the body cold sources of the intermediate heat exchanger IHX and the waste heat discharging heat exchanger DHX and the body heat source of the reactor core are controlled by writing a Users-defined function program carried in the fluent, so that the power of each component of the pool type sodium-cooled fast reactor under different working conditions is controlled to change along with time. As shown in (a) and (b) of fig. 3, the powers of the IHX and the core are time-varying under the accident condition, and in the calculation strategy, the control is also performed through an external udf program, and the power of the IHX and the core can be changed according to the rule required by the corresponding condition only by changing a corresponding function in a udf program without modifying a cas file.
Examples
Through adjusting each surface attribute of the T-shaped connecting coupling module 13 between the main pump 7 and the pressure pipe 5, different boundary conditions can be set under the condition that grids are not changed, calculation of different working conditions is carried out, and specific operation in calculation is carried out:
1) steady state conditions: when steady-state calculation is carried out, the surface c is set as an inlet boundary with constant flow and constant temperature, the surface a is a pressure outlet boundary, and all the other surfaces of the communication coupling module are set as walls;
2) transient operating mode 1, water loss accident at secondary side of steam generator: when this accident occurs, the steam generator cannot take away the heat of the secondary circuit intermediate heat exchanger 10, and accordingly, the hot sodium in the primary circuit cannot be cooled effectively, and the cooling power of the primary circuit intermediate heat exchanger 10 decreases rapidly. Within a few seconds of receiving a steam generator water loss signal, a control rod is inserted, the reactor core 2 is shut down, in order to match the change of the power in the reactor, the flow of a primary pump 7 in a circuit is gradually reduced, the temperature of the fluid is changed along with the temperature in a cold pool, therefore, in the transient condition, the flow and the temperature of an inlet are changed along with time, in udf procedure, a surface and a surface are set as the boundary condition of the flow inlet, the flow of which is changed along with time, the average temperature of the surface a is given to the fluid entering the system through the surface c, and the arrangement of the two primary pumps 7 and the pressure pipe 5 is the same, wherein the flow direction of the fluid is shown as (a) in figure 3.
3) Transient operating mode 2, a main pump card axle accident of a return circuit: in the event of this accident, assuming that the second main pump 7 of a circuit (on the right in fig. 2) is stuck and is unable to provide kinetic energy to the fluid, the second main pump 7 becomes a resistive path through which the fluid can pass. At this time, the a-side of the second main pump 7 is set to a solid side, and the b-side and the d-side of the communicative coupling block 13 are changed to internal sides, allowing the fluid to pass through the e-side, so that in the communicative coupling block of the second main pump 7, a passage is formed in which the fluid flows in the direction indicated by the arrow in fig. 3 (b). The other, intact first main pump 7 feeds the inlet flow boundary in the manner shown in figure 3 (a).
4) Transient operating mode 3, full outage accident: when the accident happens, the whole power plant loses power, the two main pumps 7 lose power and start to run down. In the idling time of the main pumps 7, the communicating coupling modules 13 of the two main pumps 7 are arranged as shown in (a) in fig. 3, and inlet flow is given according to a flow idling curve; after the idling is stopped, the communicative coupling module 13 is set as shown in fig. 3 (b), and the b-plane and the d-plane of the communicative coupling module on both sides are set as internal planes, and the a-plane and the c-plane are set as solid planes, so that the fluid can be allowed to flow in the main pump 7, and the setting of the natural circulation in the stack is satisfied.
Claims (3)
1. A fast reactor main pump circulation channel modeling calculation method based on 'virtual valve' is characterized in that a loop in a fast reactor container is a pool type sodium-cooled fast reactor loop formed by connecting two main pumps (7), a communication coupling module (13), a pressure pipe (5), a grid plate header (3) and a reactor core (2), the loop is a closed system, the b surface and the d surface of the communication coupling module (13) on the two sides are set as internal surfaces, and the a surface and the c surface are set as solid surfaces; the surface e is a channel for the fluid to enter the pump from the cold pool; the calculation of the loop three-dimensional thermal fluid transient state comprises the following steps:
step 1, respectively arranging a communication coupling module for boundary condition conversion at the joint of two main pumps and a pressure pipe of a loop, connecting the communication coupling module and an integral fast reactor model through an interface in a fluent, and adjusting the surface type of the interface in the fluent to change the flow inlet or outlet of the fast reactor model without changing grids so that one set of grid model can be used for calculating various working conditions;
step 2, reasonably simplifying a fast reactor container and reactor internals in the pool type sodium-cooled fast reactor, and establishing a detailed three-dimensional pool type sodium-cooled fast reactor model which comprises a central measuring column (1), a reactor core (2), a grid plate header (3), a main container (4), a pressure pipe (5), an in-reactor support (6), two main pumps (7), an overflow window (8), a biological shielding column (9), an intermediate heat exchanger (10), an out-of-reactor biological shielding column (11), a reactor core shield (12), a communication coupling module (13), a reactor core melting collector and a sodium extruder; the model can accurately simulate the transient working condition of the in-pile flow process, and the obtained detailed in-pile fluid three-dimensional thermal hydraulic parameters are the fluid temperature, pressure and speed at each position in the pile;
step 3, determining physical parameters of the sodium fluid, wherein the physical parameters of the sodium fluid are the density, viscosity and specific heat capacity of liquid sodium input before calculation; after calculation, obtaining three-dimensional thermal hydraulic parameters of the fluid at each position in the pile, including the temperature, the speed and the pressure of the fluid; and physical parameters of the materials of the components: the density, specific heat capacity and viscosity of sodium are adopted in fluent to change along with temperature; the body cold sources of the intermediate heat exchanger IHX and the waste heat discharging heat exchanger DHX and the body heat source of the reactor core are controlled by writing a Users-defined function program carried in the fluent, so that the power of each component of the pool type sodium-cooled fast reactor under different working conditions is controlled to change along with time.
2. The fast reactor main pump flow channel modeling calculation method based on the virtual valve according to the claim 1, characterized in that the boundary conditions of the fast reactor model are as follows: an inlet fluid is fed at the inlet of the pressure tube and a pressure outlet is fed above the pressure tube, inside the pump.
3. The fast reactor main pump flow channel modeling calculation method based on the virtual valve is characterized in that when the steady state of the three-dimensional hot working fluid of the primary circuit is calculated, an inlet and an outlet are manually given to simulate the flow of the primary circuit sodium in the reactor, the inlet is arranged at the impeller outlet of the main pump, namely the c surface where the main pump and the pressure pipe are connected in the model, the outlet is arranged on the impeller inlet a surface of the main pump in the actual model and is arranged as a pressure outlet to balance the flow of the primary circuit; the boundary conditions for different conditions are changed by changing the various face properties of the transition section and the control of inlet flow and temperature by the circumscribed line Udf under different accident conditions.
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| CN113063816B (en) * | 2021-03-23 | 2022-07-26 | 华北电力大学 | Test bench for researching thermal oscillation of central column of fast reactor plug |
| CN113343597B (en) * | 2021-06-01 | 2023-04-18 | 潍柴动力股份有限公司 | Method and device for calculating virtual pressure behind throttle valve |
| CN113657049B (en) * | 2021-08-17 | 2023-06-16 | 哈尔滨工程大学 | Heat transfer and flow quick simulation method for pool type sodium-cooled fast reactor main coolant system |
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