CN115859868B - Critical heat flow calculation method suitable for fusion reactor component under single-sided heating condition - Google Patents
Critical heat flow calculation method suitable for fusion reactor component under single-sided heating condition Download PDFInfo
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- 238000010438 heat treatment Methods 0.000 title claims abstract description 54
- 230000004927 fusion Effects 0.000 title claims abstract description 37
- 238000004364 calculation method Methods 0.000 title claims abstract description 13
- 238000000034 method Methods 0.000 claims abstract description 10
- 239000007788 liquid Substances 0.000 claims abstract description 9
- 238000009835 boiling Methods 0.000 claims abstract description 6
- 230000005514 two-phase flow Effects 0.000 claims abstract description 5
- 239000000498 cooling water Substances 0.000 claims description 52
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 9
- 229920006395 saturated elastomer Polymers 0.000 claims description 8
- 230000008859 change Effects 0.000 claims description 4
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- 238000004088 simulation Methods 0.000 abstract 1
- 238000011156 evaluation Methods 0.000 description 3
- 238000002474 experimental method Methods 0.000 description 3
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 229910052722 tritium Inorganic materials 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
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- 229910052799 carbon Inorganic materials 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000014509 gene expression Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 210000002381 plasma Anatomy 0.000 description 1
- 238000002294 plasma sputter deposition Methods 0.000 description 1
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a critical heat flow calculation method suitable for a single-sided heating condition of a fusion reactor component, which is characterized in that a gas-liquid two-phase flow model is combined with an empirical formula for calculating critical heat flow by uniformly heating a circular pipe in the circumferential direction, a gas phase share threshold under different thermodynamic conditions is obtained by adopting a numerical simulation method, the gas phase share threshold is used as a boiling critical generation criterion, gas-liquid two-phase numerical analysis is further carried out, the heat flow is gradually increased until the maximum value of the gas phase share of a heating wall surface is equal to the gas phase share threshold, and accordingly, a complex flow channel structure (critical heat flow) under the single-sided heating condition of the fusion reactor component is obtained.
Description
Technical Field
The invention belongs to the field of fusion stacks, and particularly relates to a critical heat flow calculation method suitable for a fusion stack component under a single-sided heating condition.
Background
Nuclear fusion energy has the excellent characteristics of low carbon, economy, inherent safety and the like, and is considered as an effective way capable of thoroughly solving the crisis of human energy. The magnetic confinement full-superconducting tokamak fusion reactor is expected to realize controllable and energy continuous output, deuterium and tritium plasmas are used as nuclear reaction fuels, fusion reaction is carried out under specific environment and ultra-high temperature conditions, and huge energy is released. However, plasma-facing components such as tritium breeder cladding, diverters, restrictors, and heating and diagnostic systems, are exposed to core high temperature radiation and plasma sputtering on one side, with surface heat flow up to MW/m 2 Magnitude. In order to smoothly discharge heat and prevent the temperature of materials from exceeding the standard, the design of the existing fusion reactor part mostly adopts cooling water as a heat exchange working medium, and the fusion reactor part has the advantages of low cost and strong heat carrying capacity. Under the action of high heat flow of the fusion reactor, the cooling water is easy to generate boiling phase change, the air film attached to the pipe wall can obstruct heat exchange,the heat transfer mechanism is changed. Under the critical heat flow condition, the convection heat transfer coefficient of cooling water is suddenly reduced, and the wall temperature is suddenly increased, so that the structural integrity is threatened, nuclear leakage even occurs due to a crack accident, and radioactive substances are released to pollute the environment. Thus, preparing to evaluate the critical heat flow of fusion reactor components is critical to thermal safety performance studies. Because the critical heat flow phenomenon has obvious nonlinear characteristics, the existing evaluation methods in the field of fusion stacks are mostly based on experimental results, and summary relational expressions are summarized. However, the experiment needs to be performed under high-temperature and high-pressure conditions, so that the cost is high and the period for acquiring experimental data is long. In addition, the existing experimental model is obtained by aiming at the service environment characteristics of the fuel element, the applicable object is a circular runner which is uniformly heated in the circumferential direction, and the critical heat flow of a complex runner structure (such as a rectangular smooth pipe, an inserted spoiler or a reinforced pipe with rib plates on the wall surface) which is heated on one side in the fusion reactor part is difficult to calculate.
Disclosure of Invention
In order to solve the technical problems, the invention provides a critical heat flow calculation method suitable for a fusion reactor component under a single-sided heating condition. Based on a critical heat flow empirical formula under the condition of uniform circumferential heating of a circular tube, a gas-liquid two-phase flow model analysis is used for obtaining a gas phase share threshold under different thermodynamic conditions as a boiling critical generation criterion, so that the critical heat flow of a fusion reactor component under the condition of single-sided heating under different cooling water running pressures, inlet flows and temperatures is constructed, wherein the critical heat flow of a complex flow channel structure (such as a rectangular smooth tube, an inserted spoiler or a reinforced tube with rib plates on the wall surface) is realized. The method can solve the problem that the conventional critical heat flow evaluation method is only applicable to single-sided heating conditions of fusion reactor components and complex flow channel structures aiming at uniform heating conditions in the circumferential direction of the circular tube; the problems of high cost and long period faced by obtaining critical heat flow by carrying out experiments can be solved.
In order to achieve the above purpose, the technical scheme adopted by the invention is as follows:
a critical heat flow calculation method suitable for a fusion reactor component under a single-sided heating condition comprises the following steps:
step one: based on experimental conditions for obtaining critical heat flow aiming at uniform circumferential heating of a circular tube, constructing a thermal hydraulic analysis model for uniform circumferential heating of the circular tube, wherein the thermal hydraulic analysis model comprises length, hydraulic diameter and wall thickness;
step two: applying thermodynamic conditions to the circular tube, wherein the thermodynamic conditions comprise wall heat flow, heating area, running pressure of cooling water, inlet flow and inlet temperature of the cooling water which are uniformly heated in the circumferential direction, obtaining outlet enthalpy of the cooling water through one-dimensional heat balance theoretical analysis, and further carrying out interpolation calculation between saturated water enthalpy and superheated steam enthalpy to obtain thermodynamic balance dryness of the cooling water at the outlet of the circular tube;
step three: after the thermodynamic conditions of the running pressure, the inlet temperature, the inlet flow and the thermodynamic equilibrium dryness of the cooling water at the outlet are provided, calculating to obtain critical heat flow under the thermodynamic conditions by adopting a critical heat flow empirical formula for uniformly heating the circular tube in the circumferential direction, further comparing the critical heat flow with heat flow applied by the wall surface, and repeatedly adjusting the heat flow of the wall surface to be converged to a numerical value obtained by the critical heat flow empirical formula if the critical heat flow and the heat flow are unequal, thereby determining the critical heat flow for uniformly heating the circular tube in the circumferential direction under the thermodynamic conditions;
step four: a numerical model based on uniform heating in the circumferential direction of the circular tube is constructed by adopting a gas-liquid two-phase flow model, uniform critical heat flow is applied to the circumferential direction of the tube wall of the circular tube, the running pressure, the inlet flow and the inlet temperature of cooling water are given, and the gas phase share threshold value on the heating wall surface when the critical heat flow occurs is further obtained through analysis of the wall surface unbalanced boiling model;
step five: repeatedly changing the thermodynamic conditions of the circular tube for multiple times, repeatedly calculating, and finally constructing a database of the change of the gas phase share threshold along with the running pressure, the inlet flow and the inlet temperature of the cooling water;
step six: the method comprises the steps of establishing a gas-liquid two-phase numerical model for single-sided heating of the fusion reactor component facing the complex flow channel structure of the fusion reactor component, further inquiring a database under the thermodynamic hydraulic conditions of known running pressure, inlet flow and inlet temperature of cooling water to obtain corresponding gas-phase share thresholds, then gradually increasing single-sided heating heat flow of the fusion reactor component, monitoring the gas-phase share maximum value on a heating wall surface in real time, and stopping increasing the heat flow when the gas-phase share maximum value is equal to the gas-phase share thresholds, wherein the wall surface heat flow at the moment is critical heat flow under the thermodynamic conditions and corresponding complex flow channel structures.
Further, the second step includes:
obtaining the outlet enthalpy of the cooling water through one-dimensional heat balance theoretical analysis as shown in a formula (1), and further carrying out interpolation calculation between the saturated water enthalpy and the superheated steam enthalpy, and obtaining the thermodynamic balance dryness of the cooling water at the outlet of the pipeline as shown in a formula (2):
wherein:
kg/s for inlet flow of cooling water;
Further, in the fifth step, on the premise that the operating pressure, the inlet flow rate and the inlet temperature of the cooling water are known, the database is queried to obtain the corresponding gas phase share threshold value:
wherein:
the operation pressure of cooling water is MPa;
Further, the complex flow channel structure in the step six comprises a rectangular smooth tube under the condition of single-sided heating, an inserted spoiler or a reinforced tube with rib plates on the wall surface.
Compared with the existing critical heat flow evaluation method, the method has the beneficial effects that:
1. the prior method is only aimed at circular pipe runners which are uniformly heated along the circumferential direction in the field of fission reactors, is not applicable to single-sided heating of fusion reactor components and complex runner structures (such as rectangular smooth pipes, internally inserted spoilers or reinforced pipes with rib plates on the wall surfaces, and the like), but can obtain critical heat flow of the fusion reactor components under the single-sided heating, the complex runner structures and different thermodynamic conditions (cooling water running pressure, flow and temperature), and provides powerful data support for safe design of the fusion reactor components.
2. The prior experimental method needs to have high temperature and high pressure conditions, so that the cost is high, and the period for acquiring experimental data is long.
Drawings
FIG. 1 is a flow chart of a critical heat flow calculation method suitable for a single-sided heating condition of a fusion reactor component.
Detailed Description
The present invention will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present invention more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the invention. In addition, the technical features of the embodiments of the present invention described below may be combined with each other as long as they do not collide with each other.
As shown in fig. 1, the method for calculating critical heat flow of a fusion reactor component under single-sided heating condition comprises the following steps:
step one: based on the existing experimental conditions for obtaining critical heat flow aiming at uniform circumferential heating of a circular tube, constructing a thermal hydraulic analysis model for uniform circumferential heating of the circular tube, wherein the thermal hydraulic analysis model specifically comprises length, hydraulic diameter and wall thickness;
step two: applying thermodynamic conditions to the circular tube, wherein the thermodynamic conditions comprise wall heat flow, heating area, running pressure of cooling water, flow and inlet temperature of the cooling water which are uniformly heated in the circumferential direction, obtaining outlet enthalpy of the cooling water through one-dimensional heat balance theoretical analysis as shown in a formula (1), and further carrying out interpolation calculation between saturated water enthalpy and superheated steam enthalpy as shown in a formula (2), so as to obtain thermodynamic equilibrium dryness of the cooling water at the outlet of the pipeline;
wherein:
kg/s for inlet flow of cooling water;
Step three: after the thermodynamic conditions of the running pressure, the inlet temperature, the flow and the outlet thermodynamic equilibrium dryness of the cooling water are provided, a critical heat flow empirical formula for uniformly heating the circular tube in the circumferential direction is adopted, the critical heat flow under the thermodynamic conditions is calculated and obtained, the critical heat flow is further compared with the heat flow applied to the wall surface, if the critical heat flow and the wall surface are not equal, the wall surface heat flow is repeatedly regulated to be converged to a numerical value obtained by the critical heat flow empirical formula, and therefore the critical heat flow for uniformly heating the circular tube in the circumferential direction under the thermodynamic conditions is determined;
step four: a numerical model based on uniform heating in the circumferential direction of the circular tube is constructed by adopting a gas-liquid two-phase flow model, uniform critical heat flow is applied to the circumferential direction of the tube wall of the circular tube, the running pressure, inlet flow and temperature of cooling water are given, and the gas phase share threshold value on the heating wall surface when the critical heat flow occurs is further obtained through analysis of the unbalanced boiling model of the wall surface;
step five: repeatedly changing the thermodynamic conditions of the circular tube for multiple times, repeatedly calculating, and finally constructing a database of the change of the gas phase share threshold along with the running pressure, the inlet flow and the inlet temperature of the cooling water, wherein the database can be queried to obtain the corresponding gas phase share threshold on the premise that the three parameters are known as shown in a formula (3);
wherein:
the operation pressure of cooling water is MPa;
Step six: the complex flow channel structure facing the fusion reactor component is used for constructing a gas-liquid two-phase numerical model of single-sided heating of the fusion reactor component, under the condition of knowing the running pressure, the inlet flow and the inlet temperature of cooling water, a database is further queried to obtain a corresponding gas phase share threshold value, then the single-sided heating heat flow of the fusion reactor component is gradually increased, the gas phase share maximum value on a heating wall surface is monitored in real time, when the gas phase share maximum value is equal to the gas phase share threshold value, the increase of the heat flow is stopped, and the wall surface heat flow at the moment is the critical heat flow under the thermodynamic conditions (the running pressure of cooling water, the inlet flow and the inlet temperature) and the corresponding complex flow channel structure. The complex flow channel structure comprises a rectangular smooth pipe, an inserted spoiler or a reinforced pipe with rib plates on the wall surface.
Claims (4)
1. The critical heat flow calculation method suitable for the single-sided heating condition of the fusion reactor component is characterized by comprising the following steps of:
step one: based on experimental conditions for obtaining critical heat flow aiming at uniform circumferential heating of a circular tube, constructing a thermal hydraulic analysis model for uniform circumferential heating of the circular tube, wherein the thermal hydraulic analysis model comprises length, hydraulic diameter and wall thickness;
step two: applying thermodynamic conditions to the circular tube, wherein the thermodynamic conditions comprise wall heat flow, heating area, running pressure of cooling water, inlet flow and inlet temperature of the cooling water which are uniformly heated in the circumferential direction, obtaining outlet enthalpy of the cooling water through one-dimensional heat balance theoretical analysis, and further carrying out interpolation calculation between saturated water enthalpy and superheated steam enthalpy to obtain thermodynamic balance dryness of the cooling water at the outlet of the circular tube;
step three: after the thermodynamic conditions of the running pressure, the inlet temperature, the inlet flow and the thermodynamic equilibrium dryness of the cooling water at the outlet are provided, calculating to obtain critical heat flow under the thermodynamic conditions by adopting a critical heat flow empirical formula for uniformly heating the circular tube in the circumferential direction, further comparing the critical heat flow with heat flow applied by the wall surface, and repeatedly adjusting the heat flow of the wall surface to be converged to a numerical value obtained by the critical heat flow empirical formula if the critical heat flow and the heat flow are unequal, thereby determining the critical heat flow for uniformly heating the circular tube in the circumferential direction under the thermodynamic conditions;
step four: a numerical model based on uniform heating in the circumferential direction of the circular tube is constructed by adopting a gas-liquid two-phase flow model, uniform critical heat flow is applied to the circumferential direction of the tube wall of the circular tube, the running pressure, the inlet flow and the inlet temperature of cooling water are given, and the gas phase share threshold value on the heating wall surface when the critical heat flow occurs is further obtained through analysis of the wall surface unbalanced boiling model;
step five: repeatedly changing the thermodynamic conditions of the circular tube for multiple times, repeatedly calculating, and finally constructing a database of the change of the gas phase share threshold along with the running pressure, the inlet flow and the inlet temperature of the cooling water;
step six: the method comprises the steps of establishing a gas-liquid two-phase numerical model for single-sided heating of the fusion reactor component facing the complex flow channel structure of the fusion reactor component, further inquiring a database under the thermodynamic hydraulic conditions of known running pressure, inlet flow and inlet temperature of cooling water to obtain corresponding gas-phase share thresholds, then gradually increasing single-sided heating heat flow of the fusion reactor component, monitoring the gas-phase share maximum value on a heating wall surface in real time, and stopping increasing the heat flow when the gas-phase share maximum value is equal to the gas-phase share thresholds, wherein the wall surface heat flow at the moment is critical heat flow under the thermodynamic conditions and corresponding complex flow channel structures.
2. The method for calculating critical heat flow under single-sided heating conditions of a fusion reactor component according to claim 1, wherein the second step comprises:
obtaining the outlet enthalpy of the cooling water through one-dimensional heat balance theoretical analysis as shown in a formula (1), and further carrying out interpolation calculation between the saturated water enthalpy and the superheated steam enthalpy, and obtaining the thermodynamic balance dryness of the cooling water at the outlet of the pipeline as shown in a formula (2):
wherein:
kg/s for inlet flow of cooling water;
3. The method for calculating critical heat flow under single-sided heating conditions of a fusion reactor component according to claim 2, wherein in the fifth step, on the premise that the operating pressure, the inlet flow and the inlet temperature of cooling water are known, a database is queried to obtain a corresponding gas phase share threshold value:
wherein:
the operation pressure of cooling water is MPa;
4. The method for calculating critical heat flow under single-sided heating conditions of a fusion reactor component according to claim 3, wherein the complex flow channel structure in the sixth step comprises a rectangular smooth tube, an inserted spoiler or a reinforced tube with rib plates on the wall surface under single-sided heating conditions.
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| CN111753473A (en) * | 2020-06-24 | 2020-10-09 | 国核自仪系统工程有限公司 | Method, system, medium and apparatus for assessing critical heat flux of pressure vessel |
| CN115440395A (en) * | 2022-09-30 | 2022-12-06 | 中国科学院合肥物质科学研究院 | Flowing heat extraction structure in low-melting-point metal tube suitable for fusion reactor strong magnetic field and high heat flow environment |
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