Modeling warming the fuel cell in a nuclear reactor
The importance of involving customers in the innovation process in relation to marketing innovation and marketing innovation, retro shapes hr self service td of display screen LCDs PI controller hr self service td design method with Desired phase margin and settling time Trigonometric analysis coaxial hr self service td stereoscopic camera system Remote monitoring of temperature in a static kiln
This work deals with modeling of temperature field in the fuel cell nuclear reactor, while examining the impact of heat generated on its warming for different load cases. Modeling and simulation was performed by finite element program ANSYS on the chosen spatial model of the fuel cell.
The temperature of the fuel cell in a nuclear reactor for safe operation shall not exceed the permissible value. Therefore, its temperature measured or simulated warming of analytical and numerical methods. In the present work we deal with assembling the fuel cell model, which we use to determine the steady warming of the selected boundary conditions. To compare the results, we chose a simplified model of a fuel cell with a homogeneous heat generation using rotational symmetry task. All tasks are modeled in ANSYS [1].
Warming the fuel cell was solved by finite element method (FEM). MLP is: a computer-oriented problems solution in field theory (strength, deformation, electrostatic, electromagnetic, temperature, speed, radiation, etc.) approximate method of solving the system of partial differential equations (dif. equilibrium equations, differential. Equation of heat conduction, el. current, electromagnetic induction, etc.)
Principle: hr self service td the initial state of the body (strength, deformation, temperature, ...) describing the functionalities (feature functions) that contains the relevant known and unknown state variables (force, stress, strain, initial temperature, pressure, hr self service td speed of movement, ...) for some area (surface or volume of the body). hr self service td It must also find the value of an unknown quantity in the body paragraphs (displacement, temperature, speed) that make the functional stationary. As a rule, the minimum functional search for the initial and boundary conditions. Finding stationary values of functionals deals calculus of variations [7].
The output hr self service td of the method: the immediate state of the body (strain and tightness hr self service td in the body paragraphs, temperature distribution, movement speed, custom shapes and natural frequencies of the system, the electric hr self service td potential, current density, power loss, etc ...).
For modeling of the fuel cell, the amount of which is 2.536 m, we assume that the temperature field varies in the longitudinal and radial direction of the fuel cell. A fuel cell consists of 5 parts, as can be seen in Fig. 1 The most important is the part where the uranium, which generates heat. Basic dimensions of the fuel cell is taken from [2].
The individual parts of the fuel cell is characterized by a thermal conductivity λ, which is temperature dependent. For uranium is given dependence of thermal conductivity λ of temperature is significant, as can be seen in Fig. 2 [2].
In addressing the temperature of the fuel cell as axisymmetric problems, we assumed that the fuel cell cooling water bypassing the primary circuit of a nuclear power plant at a temperature of 300 C. In real VVER 440 is a cooling water inlet temperature 267 C and cooling water outlet 297 C. The value of the coefficient of convective heat transfer, we chose α = 35 000 W / m 2 K [2].
Analyzed the performance of individual fuel rods across the core commitments hr self service td based on a representative core. Hot wand - the wand with maximum power, which is actually not in the core, but we are considering hr self service td it for modeling. Its capacity is 1,692 - times that of the average wand [6]. Average wand - wand in the core, with an average heat output [6]: 1 471.25 MW, 349/126 = 33.46 kW. Frequency of rods in each group is shown in the following (Table 2) [6].
Tab. 2 Division of rods in the core group times that of the avg. Max wand. wand power [kW] Number of rods 1 Number of cartridges <min-0.8> 26.77 9312 74 2 (0.8 - 1.2> 33.46 23286 185 3 (1.2 - 1.4> 40.15 9300 74 4 (1.4 - HP> 56, 2076 60 16 Total 43 974 349
Tab. 3 Division of twigs for the calculation in thermal performance times that of the average PP value used in calculating the designation in the calculations 0.8 26.768 0.8 PPP 1 kW 33.46 kW Average wand kW 1.2 1.2 40.152 1.4 46.844 kW PPP PPP 1.4 1, 7 56.6 kW hot wand
Of Fig. 3, Fig. 4, Fig. 5 is displayed temperature field in different parts of the fuel cell. For his height, which reaches 2.534 meters, the fuel cell graphically divided into 3 parts: the upper end, middle part and the lower end.
We see that, the maximum temperature is 975.703 º C. The highest temperature hr self service td is in respect of uranium, and a small gap, where gases are collected. Fuel cell gradually hr self service td in the direction of x-axis of the outer wall cool, which dissipates heat and
The importance of involving customers in the innovation process in relation to marketing innovation and marketing innovation, retro shapes hr self service td of display screen LCDs PI controller hr self service td design method with Desired phase margin and settling time Trigonometric analysis coaxial hr self service td stereoscopic camera system Remote monitoring of temperature in a static kiln
This work deals with modeling of temperature field in the fuel cell nuclear reactor, while examining the impact of heat generated on its warming for different load cases. Modeling and simulation was performed by finite element program ANSYS on the chosen spatial model of the fuel cell.
The temperature of the fuel cell in a nuclear reactor for safe operation shall not exceed the permissible value. Therefore, its temperature measured or simulated warming of analytical and numerical methods. In the present work we deal with assembling the fuel cell model, which we use to determine the steady warming of the selected boundary conditions. To compare the results, we chose a simplified model of a fuel cell with a homogeneous heat generation using rotational symmetry task. All tasks are modeled in ANSYS [1].
Warming the fuel cell was solved by finite element method (FEM). MLP is: a computer-oriented problems solution in field theory (strength, deformation, electrostatic, electromagnetic, temperature, speed, radiation, etc.) approximate method of solving the system of partial differential equations (dif. equilibrium equations, differential. Equation of heat conduction, el. current, electromagnetic induction, etc.)
Principle: hr self service td the initial state of the body (strength, deformation, temperature, ...) describing the functionalities (feature functions) that contains the relevant known and unknown state variables (force, stress, strain, initial temperature, pressure, hr self service td speed of movement, ...) for some area (surface or volume of the body). hr self service td It must also find the value of an unknown quantity in the body paragraphs (displacement, temperature, speed) that make the functional stationary. As a rule, the minimum functional search for the initial and boundary conditions. Finding stationary values of functionals deals calculus of variations [7].
The output hr self service td of the method: the immediate state of the body (strain and tightness hr self service td in the body paragraphs, temperature distribution, movement speed, custom shapes and natural frequencies of the system, the electric hr self service td potential, current density, power loss, etc ...).
For modeling of the fuel cell, the amount of which is 2.536 m, we assume that the temperature field varies in the longitudinal and radial direction of the fuel cell. A fuel cell consists of 5 parts, as can be seen in Fig. 1 The most important is the part where the uranium, which generates heat. Basic dimensions of the fuel cell is taken from [2].
The individual parts of the fuel cell is characterized by a thermal conductivity λ, which is temperature dependent. For uranium is given dependence of thermal conductivity λ of temperature is significant, as can be seen in Fig. 2 [2].
In addressing the temperature of the fuel cell as axisymmetric problems, we assumed that the fuel cell cooling water bypassing the primary circuit of a nuclear power plant at a temperature of 300 C. In real VVER 440 is a cooling water inlet temperature 267 C and cooling water outlet 297 C. The value of the coefficient of convective heat transfer, we chose α = 35 000 W / m 2 K [2].
Analyzed the performance of individual fuel rods across the core commitments hr self service td based on a representative core. Hot wand - the wand with maximum power, which is actually not in the core, but we are considering hr self service td it for modeling. Its capacity is 1,692 - times that of the average wand [6]. Average wand - wand in the core, with an average heat output [6]: 1 471.25 MW, 349/126 = 33.46 kW. Frequency of rods in each group is shown in the following (Table 2) [6].
Tab. 2 Division of rods in the core group times that of the avg. Max wand. wand power [kW] Number of rods 1 Number of cartridges <min-0.8> 26.77 9312 74 2 (0.8 - 1.2> 33.46 23286 185 3 (1.2 - 1.4> 40.15 9300 74 4 (1.4 - HP> 56, 2076 60 16 Total 43 974 349
Tab. 3 Division of twigs for the calculation in thermal performance times that of the average PP value used in calculating the designation in the calculations 0.8 26.768 0.8 PPP 1 kW 33.46 kW Average wand kW 1.2 1.2 40.152 1.4 46.844 kW PPP PPP 1.4 1, 7 56.6 kW hot wand
Of Fig. 3, Fig. 4, Fig. 5 is displayed temperature field in different parts of the fuel cell. For his height, which reaches 2.534 meters, the fuel cell graphically divided into 3 parts: the upper end, middle part and the lower end.
We see that, the maximum temperature is 975.703 º C. The highest temperature hr self service td is in respect of uranium, and a small gap, where gases are collected. Fuel cell gradually hr self service td in the direction of x-axis of the outer wall cool, which dissipates heat and
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