CN115859868A - 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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Abstract
The invention discloses a critical heat flow calculation method suitable for a fusion reactor component under a single-side heating condition, which is characterized in that a gas-liquid two-phase flow model is combined with an empirical formula for calculating critical heat flow by circumferential uniform heating of a circular tube, gas phase share threshold values under different thermodynamic conditions are obtained by adopting a numerical simulation method and are used as criterion for boiling critical generation, gas-liquid two-phase numerical analysis is further carried out, 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 value, and accordingly (critical heat flow of) a complex flow channel structure under a single-side heating condition in the fusion reactor component is obtained.
Description
Technical Field
The invention belongs to the field of fusion reactors, and particularly relates to a critical heat flow calculation method suitable for a fusion reactor component under a single-sided heating condition.
Background
The nuclear fusion energy has the excellent characteristics of low carbon, economy, inherent safety and the like, and is considered to be an effective way for thoroughly solving the energy crisis of human beings. The magnetic confinement full-superconducting tokamak fusion reactor is expected to realize controllable and energy continuous output, and deuterium and tritium plasmas are used as nuclear reaction fuels to generate fusion reaction under specific environment and ultrahigh temperature conditions to release huge energy. However, plasma-facing components, such as tritium breeder cladding, diverters, limiters, and heating and diagnostic systems, suffer from core high temperature radiation and plasma sputtering on one side, with surface heat flux up to MW/m 2 Magnitude. In order to smoothly discharge heat and prevent the temperature of materials from exceeding the standard, the existing fusion reactor part is designed to mostly adopt cooling water as a heat exchange working medium, and has the advantages of low price and strong heat carrying capacity. Under the action of high heat flow of the fusion reactor, cooling water is easy to generate boiling phase change, and an air film attached to the tube wall can block heat exchange, so that the heat transfer mechanism is changed. Under the condition of critical heat flow, the convective heat transfer coefficient of cooling water drops sharply, and the wall temperature rises in a step mode, so that the structural integrity is threatened, even nuclear leakage occurs in the event of a breach accident, radioactive substances are released, and the environment is polluted. Thus, the critical heat of fusion reactor components is ready to be evaluatedThe flow is important for the research of thermal safety characteristics. Because the critical heat flow phenomenon has obvious nonlinear characteristics, the existing evaluation method in the fusion reactor field is mostly based on experimental results, and a summary relational expression is summarized. However, the development of experiments requires high temperature and high pressure conditions, which results in high cost and long period for acquiring experimental data. 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 flow channel which is uniformly heated in the circumferential direction, and the critical heat flow of a complex flow channel structure (such as a rectangular smooth pipe, an inserted spoiler or a reinforced pipe with a ribbed plate 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 problem, the invention provides a critical heat flow calculation method suitable for a fusion reactor component under a single-sided heating condition. On the basis of a critical heat flow empirical formula under a circular tube circumferential uniform heating condition, gas phase share threshold values under different thermodynamic conditions are obtained through gas-liquid two-phase flow model analysis and serve as a criterion for boiling critical generation, and critical heat flows of complex flow channel structures (such as rectangular smooth tubes, inserted spoilers or reinforced tubes with ribbed plates on the wall surfaces) of fusion reactor components under single-sided heating conditions under different cooling water operating pressures, inlet flows and temperatures are constructed accordingly. The invention can solve the problems that the existing critical heat flow evaluation method only aims at the circumferential uniform heating condition of a circular tube, but is not applicable to the single-side heating condition of a fusion reactor part and a complex flow channel structure; the problems of high cost and long period of critical heat flow obtained by carrying out experiments can be solved.
In order to achieve the 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-side heating condition comprises the following steps:
the method comprises the following steps: constructing a thermal hydraulic analysis model for uniformly heating the circumferential direction of the circular tube based on the experimental conditions for obtaining critical heat flow by uniformly heating the circumferential direction of the circular tube, wherein the thermal hydraulic analysis model comprises length, hydraulic diameter and wall thickness;
step two: applying thermal hydraulic conditions to the circular tube, wherein the thermal hydraulic conditions comprise wall surface heat flow which is uniformly heated in the circumferential direction, a heating area, the running pressure of cooling water, the inlet flow and the inlet temperature of the cooling water, obtaining the outlet enthalpy of the cooling water through one-dimensional thermal balance theoretical analysis, and then performing interpolation calculation between saturated water enthalpy and superheated steam enthalpy to obtain the thermodynamic balance dryness of the cooling water at the outlet of the circular tube;
step three: after the thermodynamic condition of the thermodynamic equilibrium dryness of the cooling water at the running pressure, the inlet temperature, the inlet flow and the outlet of the cooling water is met, the critical heat flow empirical formula of the circumferential uniform heating of the circular tube is adopted to calculate and obtain the critical heat flow under the thermodynamic condition, the critical heat flow is further compared with the heat flow applied by the wall surface, if the critical heat flow empirical formula and the heat flow are not equal, the heat flow of the wall surface is repeatedly adjusted to converge on the value obtained through the critical heat flow empirical formula, and therefore the critical heat flow of the circumferential uniform heating of the circular tube under the thermodynamic condition is determined;
step four: a numerical model based on circumferential uniform heating of a 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 a gas phase share threshold value on the heating wall surface when the critical heat flow occurs is further obtained through analysis of a wall surface non-equilibrium boiling model;
step five: changing the thermodynamic conditions of the circular tube for many times, repeatedly calculating, and finally constructing a database of the gas phase share threshold value changing along with the operating 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-side heating of the fusion reactor component facing to a complex flow channel structure of the fusion reactor component, further inquiring a database to obtain a corresponding gas-phase share threshold value under the thermal hydraulic condition of known running pressure, inlet flow and inlet temperature of cooling water, then gradually increasing the single-side heating heat flow of the fusion reactor component, monitoring the maximum value of the gas-phase share on a heating wall surface in real time, stopping increasing the heat flow when the maximum value of the gas-phase share is equal to the gas-phase share threshold value, and obtaining the wall heat flow at the moment as the critical heat flow under the thermal hydraulic condition and the corresponding complex flow channel structure.
Further, the second step comprises:
through one-dimensional heat balance theory analysis, as shown in formula (1), the outlet enthalpy of the cooling water is obtained, then interpolation calculation is carried out between the saturated water enthalpy and the superheated steam enthalpy, as shown in formula (2), the thermodynamic balance dryness of the cooling water at the outlet of the pipeline is obtained:
in the formula:
the inlet flow rate of cooling water is kg/s;
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, querying a database to obtain a corresponding gas phase share threshold value:
in the formula:
the operating pressure of the cooling water is MPa;
Further, the complex flow channel structure in the sixth step comprises a rectangular smooth pipe, an inserted spoiler or a reinforced pipe with ribbed plates on the wall surface under a single-sided heating condition.
Compared with the existing critical heat flow evaluation method, the method has the advantages that:
1. the conventional method only aims at circular tube runners uniformly heated along the circumferential direction in the fission reactor field, and is not suitable for single-side heating of fusion reactor parts and complex runner structures (such as rectangular smooth tubes, inserted spoilers or reinforced tubes with ribbed plates on the wall surface and the like).
2. The existing 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 method for calculating critical heat flow of a fusion reactor component under a single-sided heating condition.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention. In addition, the technical features involved in the embodiments of the present invention described below may be combined with each other as long as they do not conflict with each other.
As shown in fig. 1, the method for calculating critical heat flow of a fusion reactor component under a single-sided heating condition includes the following steps:
the method comprises the following steps: constructing a thermal hydraulic analysis model for uniformly heating the circumferential direction of the circular tube based on the existing experimental conditions for obtaining critical heat flow by uniformly heating the circumferential direction of the circular tube, wherein the thermal hydraulic analysis model specifically comprises length, hydraulic diameter and wall thickness;
step two: applying thermal hydraulic conditions to the circular tube, wherein the thermal hydraulic conditions specifically comprise wall surface heat flow which is uniformly heated in the circumferential direction, a heating area, the operating pressure of cooling water, the flow rate of the cooling water and the inlet temperature, obtaining the outlet enthalpy of the cooling water through one-dimensional thermal balance theoretical analysis, as shown in a formula (1), and then performing interpolation calculation between saturated water enthalpy and superheated steam enthalpy, as shown in a formula (2), so as to obtain the thermodynamic equilibrium dryness of the cooling water at the outlet of the pipeline;
in the formula:
the inlet flow rate of cooling water is kg/s;
Step three: after the thermodynamic conditions of the running pressure, the inlet temperature, the flow rate and the outlet thermodynamic equilibrium dryness of the cooling water are met, a critical heat flow empirical formula for uniformly heating the circumferential direction of the circular tube is adopted to calculate and obtain the critical heat flow under the thermodynamic conditions of the thermal technology, the critical heat flow is further compared with the heat flow applied to the wall surface, and if the critical heat flow and the heat flow are not equal, the heat flow of the wall surface is repeatedly adjusted to converge on the value obtained through the critical heat flow empirical formula, so that the critical heat flow for uniformly heating the circular tube along the circumferential direction under the thermodynamic conditions of the thermal technology is determined;
step four: a gas-liquid two-phase flow model is adopted to construct a numerical model based on circumferential uniform heating of a circular tube, uniform critical heat flow is applied to the circumferential direction of the wall of the circular tube, the running pressure, inlet flow and temperature of cooling water are given, and a gas phase share threshold value on a heating wall surface when the critical heat flow occurs is further obtained through analysis of a wall surface non-equilibrium boiling model;
step five: changing the thermodynamic conditions of the circular tube for many times, calculating repeatedly, and finally constructing a database of the gas phase share threshold value changing along with the running pressure, the inlet flow and the inlet temperature of the cooling water, as shown in a formula (3), wherein on the premise that the three parameters are known, the database can be inquired to obtain the corresponding gas phase share threshold value;
in the formula:
the operating pressure of the cooling water is MPa;
Step six: the method comprises the steps of establishing a gas-liquid two-phase numerical model for single-side heating of the fusion reactor component facing to a complex flow channel structure of the fusion reactor component, further inquiring a database to obtain a corresponding gas-phase share threshold value under the condition of known running pressure, inlet flow and inlet temperature of cooling water, then gradually increasing single-side heating heat flow of the fusion reactor component, monitoring the maximum value of the gas-phase share on a heating wall surface in real time, stopping increasing the heat flow when the maximum value of the gas-phase share is equal to the gas-phase share threshold value, and obtaining the wall surface heat flow at the moment as the critical heat flow under the thermal-engineering hydraulics condition (the running pressure of the cooling water, the inlet flow and the inlet temperature) and the corresponding complex flow channel structure. The complex flow passage structure comprises a rectangular smooth pipe, an inserted spoiler or a reinforced pipe with ribbed plates on the wall surface.
Claims (4)
1. A critical heat flow calculation method suitable for a fusion reactor component under a single-sided heating condition is characterized by comprising the following steps of:
the method comprises the following steps: constructing a thermal hydraulic analysis model for uniformly heating the circumferential direction of the circular tube based on experimental conditions for obtaining critical heat flow by uniformly heating the circumferential direction of the circular tube, wherein the thermal hydraulic analysis model comprises length, hydraulic diameter and wall thickness;
step two: applying thermal hydraulic conditions to the circular tube, wherein the thermal hydraulic conditions comprise wall surface heat flow which is uniformly heated in the circumferential direction, a heating area, the running pressure of cooling water, the inlet flow and the inlet temperature of the cooling water, obtaining the outlet enthalpy of the cooling water through one-dimensional thermal balance theoretical analysis, and then interpolating between saturated water enthalpy and superheated steam enthalpy to obtain the thermodynamic equilibrium dryness of the cooling water at the outlet of the circular tube;
step three: after the thermodynamic condition of the thermodynamic equilibrium dryness of the cooling water at the running pressure, the inlet temperature, the inlet flow and the outlet of the cooling water is met, the critical heat flow empirical formula of the circumferential uniform heating of the circular tube is adopted to calculate and obtain the critical heat flow under the thermodynamic condition, the critical heat flow is further compared with the heat flow applied by the wall surface, if the critical heat flow empirical formula and the heat flow are not equal, the heat flow of the wall surface is repeatedly adjusted to converge on the value obtained through the critical heat flow empirical formula, and therefore the critical heat flow of the circumferential uniform heating of the circular tube under the thermodynamic condition is determined;
step four: a numerical model based on circumferential uniform heating of a 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 a gas phase share threshold value on the heating wall surface when the critical heat flow occurs is further obtained through analysis of a wall surface non-equilibrium boiling model;
step five: changing the thermal hydraulic conditions of the round pipe for many times, calculating repeatedly, and finally constructing a database of the gas phase share threshold value along with the change of 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-side heating of the fusion reactor component facing to a complex flow channel structure of the fusion reactor component, further inquiring a database to obtain a corresponding gas-phase share threshold value under the thermal hydraulic condition of known running pressure, inlet flow and inlet temperature of cooling water, then gradually increasing the single-side heating heat flow of the fusion reactor component, monitoring the maximum value of the gas-phase share on a heating wall surface in real time, stopping increasing the heat flow when the maximum value of the gas-phase share is equal to the gas-phase share threshold value, and obtaining the wall heat flow at the moment as the critical heat flow under the thermal hydraulic condition and the corresponding complex flow channel structure.
2. The method of claim 1, wherein the second step comprises:
through one-dimensional heat balance theory analysis, as shown in formula (1), the outlet enthalpy of the cooling water is obtained, and then interpolation calculation is performed between the saturated water enthalpy and the superheated steam enthalpy, as shown in formula (2), the thermodynamic balance dryness of the cooling water at the outlet of the pipeline is obtained:
in the formula:
the inlet flow rate of cooling water is kg/s;
3. The method for calculating the critical heat flow of a fusion reactor component under a single-sided heating condition as claimed in claim 2, wherein in the step five, under the condition 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 fraction threshold value:
in the formula:
the operating pressure of the cooling water is MPa;
4. The method as claimed in claim 3, wherein the complex flow channel structure in the sixth step includes a smooth rectangular tube, an inserted spoiler, or a reinforced tube with ribs on its wall surface under the condition of single-sided heating.
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| US20040069451A1 (en) * | 2002-08-06 | 2004-04-15 | Meyer Michael T. | Apparatus for heat transfer and critical heat flux enhancement |
| 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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