CN118246291A - Analysis method for flow-induced vibration of gas cooled reactor belt wire-wound fuel rod - Google Patents

Analysis method for flow-induced vibration of gas cooled reactor belt wire-wound fuel rod Download PDF

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CN118246291A
CN118246291A CN202410459203.0A CN202410459203A CN118246291A CN 118246291 A CN118246291 A CN 118246291A CN 202410459203 A CN202410459203 A CN 202410459203A CN 118246291 A CN118246291 A CN 118246291A
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calculation
fluid
domain
fuel rod
model
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章静
郭宏建
巫英伟
苏光辉
田文喜
秋穗正
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Xian Jiaotong University
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Xian Jiaotong University
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Abstract

A method for analyzing flow-induced vibration of a fuel rod with a wire winding in a gas cooled reactor includes modeling according to a fuel rod with a wire winding positioning mode, dividing grids aiming at a fluid domain and a solid domain respectively, and setting a fluid-solid coupling interface; and calling a helium physical property relation before calculation of the fluid domain part, and monitoring the change trend of the average pressure of the surface of the fuel rod along with time on the fluid-solid coupling interface. And the fluid domain adopts a large vortex simulation model, and a WALE model is selected as a sub-lattice stress model, and transient calculation is performed until convergence. The solid domain part is provided with a fixed end face, and a fluid domain pressure field is loaded on the fluid-solid coupling interface until the finite element calculation of each time step of the solid domain is converged; and carrying out frequency domain power spectral density function analysis on the fluid exciting force and the vibration displacement. The invention provides assessment and guidance for the problems of flow induced vibration and fretting wear caused by vibration of the positioning fuel rod bundle of the gas cooled reactor wire winding.

Description

Analysis method for flow-induced vibration of gas cooled reactor belt wire-wound fuel rod
Technical Field
The invention relates to the technical field of reactor flow induced vibration analysis, in particular to a method for analyzing flow induced vibration of a fuel rod with a wire wound gas cooled reactor.
Background
Gas cooled reactors are a type of reactor that uses a gas such as helium as a coolant. The reactor core of the gas cooled reactor is compact in design, and helium is obviously stirred in the flow channel due to the characteristics of compressibility, high flow rate and the like, and the flow process can cause severe fluctuation of the surface pressure of the fuel rod, so that the vibration of the fuel rod is generated. And the fuel assembly is in the severe condition of high irradiation and high service temperature for a long time, and when the bar bundles vibrate under the dynamic impact of the gas coolant to cause fatigue damage, the oxidation layer is abraded and peeled off to further aggravate corrosion, and the long refueling cycle requirement highlights the problems, so that the design, the safety and the reliability of the gas cooled reactor are verified to be influenced. It is therefore particularly important to evaluate the response mechanism of dense fuel bundles at high gas cooled reactor coolant velocity. Stability and integrity studies of fuel assemblies under coolant flushing are also important technical bottlenecks for gas cooled stacks, and reliability is one of the key factors in determining gas cooled stack design and safety characteristics.
Vibration abrasion between the spacer grid and the fuel rods in the pressurized water reactor accounts for up to 55% of the fuel damage leakage rate of the pressurized water reactor. Some of the gas cooled reactor fuel assemblies use metal spiral wire windings to position and maintain radial gaps of the bundles to compact the reactor core and improve heat exchange efficiency, and other types of helium and the like have similar vibration failure phenomena in densely arranged fuel bundles of the reactor core due to compressibility and high flow speed in the flowing process. As burnup deepens, core swelling and cladding thermal expansion reduce or even contact the wire wrap with adjacent fuel rod gaps, and high flow rate coolant flushes the fuel rod bundles to generate significant additional force to induce vibration; positioning the wire-wrap disturbance boundary layer causes intense turbulent mixing, and the axial and circumferential anisotropies of the flow field of the fuel assembly are more remarkable, so that vibration is aggravated. The high frequency and high amplitude vibration response causes fatigue damage to the fuel element, and accelerates corrosion damage to the fuel element cladding.
Since gas cooled reactors are one of the new reactor types in the field of reactors, research has been conducted in various countries in the discovery phase, and less research has been conducted on locating flow-induced vibrations of fuel rods around wires in gas cooled reactors. Considering the complexity of the flow induced vibration problem, the flow induced vibration in the reactor core is mainly based on a numerical simulation method, and an analysis method is mainly concentrated on unidirectional fluid-solid coupling of a fluid domain and a solid domain of a single wire-wrapped fuel rod, so that analysis on a wire-wrapped positioning assembly formed by a plurality of fuel rods is lacking.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention aims to provide an analysis method for flow-induced vibration of a gas cooled reactor strip wire-wound fuel rod.
In order to achieve the above purpose, the invention adopts the following technical scheme:
An analysis method for flow induced vibration of a gas cooled reactor wire winding positioning fuel rod is characterized by comprising the following steps: the method comprises the following steps:
An analysis method for flow induced vibration of a gas cooled reactor belt wound wire fuel rod comprises the following steps:
step 1: modeling a wire winding rod assembly geometric model: modeling according to a fuel rod assembly in a wire winding positioning mode, wherein the modeling comprises a fluid domain and a solid domain, and the three-dimensional geometry of a flow channel with a wire winding rod assembly and the three-dimensional geometry of a wire winding rod assembly structure are obtained;
step 2: the three-dimensional geometry of the flow channel of the filament winding rod bundle assembly is subjected to grid division to meet the requirement of a subsequent large vortex simulation model, namely an LES model, and the method comprises the following specific steps of:
Step 2-1: a fluid domain grid is primarily divided by adopting a polyhedral and prismatic layer mixed grid method so as to meet the requirement that the wall surface y+ is less than 1;
Step 2-2: dividing grids with different sizes, carrying out simulation calculation under the same boundary condition by using the RANS model to carry out grid independence analysis, and determining the minimum grid number meeting calculation;
Step 2-3: using the calculation result of the RANS model to estimate the mesh size satisfying the LES model, the specific formula is as follows:
Δ=max(λ,L/10) (1)
Wherein, delta-basic grid size/m, lambda-Taylor girth scale/m, L-turbulence energy length scale/m; the calculation expressions are respectively:
Wherein, k-turbulence energy/m 2·s-2, v-kinematic viscosity/m 2·s-1, epsilon-energy dissipation rate;
step 2-4: repartitioning the fluid domain mesh according to the estimated mesh size;
step 3: grid division is carried out on the solid domain, namely the three-dimensional geometry of the wire winding rod bundle assembly structure, and grid independence analysis is carried out;
step 4: CFD calculation of the flow channel of the wire-wrapped bundle assembly: the fluid domain calculation is carried out by adopting a computational fluid dynamics method to obtain a pressure field and a speed field of each time step in the transient calculation time period, and the method comprises the following steps:
Step 4-1: inputting an initial speed and an initial pressure of an inlet of a fuel rod bundle channel as steady-state calculation initial values, and adopting a RANS model as a turbulence model of steady-state calculation;
Step 4-2: invoking a helium physical property parameter table, selecting the density, specific heat capacity, thermal conductivity and viscosity of helium according to the temperature of the gas cooled reactor core under the normal working condition, and performing steady-state calculation until the steady-state calculation reaches convergence, so as to obtain a steady-state pressure field and a speed field of a fuel rod bundle channel, and taking the steady-state pressure field and the speed field as initial values of transient calculation;
step 4-3: the turbulence model in the transient calculation of the fluid domain adopts an LES model, a filtering mode adopts box type filtering, a WALE sub-lattice stress model is selected by the sub-lattice stress model, the transient calculation is carried out until the residual error of the transient calculation of the fluid reaches the convergence condition of 0.001, and the pressure field of the fluid changing along with the time is obtained through calculation;
Step 5: fluid-solid coupling interface pressure and shear stress distribution analysis: carrying out frequency domain analysis on the value of the fluid exciting force of each time step through a periodogram method to obtain the result of a power spectrum density function of the fluid exciting force, outputting the value of pressure and shearing force of each axial position on the surface of the fuel rod at each moment, and analyzing the influence of the pressure and the shearing force on the positioning of the fuel rod by wire winding;
Step 6: flow induced vibration time domain analysis of the wire-wrapped bundle assembly: loading a pressure field of fluid obtained by fluid domain calculation along with time change on a fluid-solid coupling interface, fixing two axial ends of a fuel assembly, carrying out solid domain calculation, respectively selecting a middle position fuel rod of a rod bundle and one surrounding fuel rod for analysis calculation until finite element calculation of each time step is converged, and obtaining vibration displacement of different points on the surface of the fuel rod at different positions of each time step;
step 7: flow induced vibration frequency domain analysis of the wire winding rod bundle assembly: carrying out frequency domain analysis on vibration displacement of different points on the surface of the fuel rod at different positions of each time step by a periodogram method to obtain a result of a power spectral density function of the vibration displacement;
Step 8: natural frequency analysis of the wire-wrapped bundle assembly: obtaining the inherent frequencies of all orders of the wire-wound rod bundle assembly through prestress modal analysis; and comparing the frequency domain analysis result in the step 7 with the natural frequency result, and analyzing the relation between the vibration of the fuel rod at different positions and the natural frequency.
Compared with the prior art, the invention has the following advantages:
1. The analysis method can analyze the flow induced vibration of the wire-wound fuel rod bundle assembly, and provides a basis for calculating the vibration abrasion among the fuel rods in the assembly;
2. according to the invention, a large vortex simulation model is adopted for calculating the fluid domain, so that turbulent flow pulsation characteristics can be better captured, and the simulation of fluid exciting force is more accurate;
3. according to the analysis method, through the analysis of the vibration displacement response in the time domain and the frequency domain, the vibration responses of the fuel rods at any positions and different axial heights on the fuel rods can be obtained, and the universality of the method is improved.
Drawings
FIG. 1 is a block diagram of a computing flow of the present invention.
FIG. 2 is a schematic view of a gas cooled reactor filament positioning fuel assembly.
Detailed Description
The process according to the invention is described in further detail below with reference to the attached drawings and to the detailed description:
as shown in FIG. 1, the method for analyzing the flow-induced vibration of the gas cooled reactor wire winding positioning fuel rod comprises the following steps:
step 1: modeling a wire winding rod assembly geometric model: modeling is carried out according to the fuel rod assembly in a wire winding positioning mode, wherein the modeling comprises a fluid domain and a solid domain, the three-dimensional geometry of a flow channel with a wire winding rod bundle assembly and the three-dimensional geometry of a wire winding rod bundle assembly structure are obtained, and 7 wire winding fuel rods are arranged in a hexagonal arrangement mode as shown in fig. 2;
Step 2: the three-dimensional geometry of the flow channel of the filament winding rod bundle assembly is subjected to grid division to meet the requirement of a subsequent large vortex simulation (LES) model, and the method comprises the following specific steps of:
Step 2-1: a fluid domain grid is primarily divided by adopting a polyhedral and prismatic layer mixed grid method so as to meet the requirement that the wall surface y+ is less than 1;
Step 2-2: dividing grids with different sizes, carrying out simulation calculation under the same boundary condition by using the RANS model to carry out grid independence analysis, and determining the minimum grid number meeting calculation;
Step 2-3: the calculation result of the RANS model is used for estimating the mesh size requirement meeting the LES model, and the specific formula is as follows:
Δ=max(λ,L/10) (1)
Where Δ -grid size/m, λ -Taylor's girth scale/m, L-turbulence energy length scale/m. The calculation expressions are respectively:
Wherein, k-turbulence energy/m 2·s-2, v-kinematic viscosity/m 2·s-1, epsilon-energy dissipation rate;
Step 2-4: the fluid domain mesh is repartitioned according to the estimated mesh size.
Step 3: and dividing a solid domain grid by adopting a tetrahedral grid, and analyzing the grid independence.
Step 4: CFD calculation of the flow channel of the wire-wrapped bundle assembly: the fluid domain calculation is carried out by adopting a computational fluid dynamics method to obtain a pressure field and a speed field of each time step in the transient calculation time period, and the method comprises the following steps:
Step 4-1: inputting a high initial speed and an initial pressure of an inlet of a fuel rod bundle channel as steady-state calculation initial values, and adopting a RANS model as a turbulence model of steady-state calculation;
step 4-2: invoking a helium physical property parameter table, selecting density, specific heat capacity, heat conductivity and viscosity equivalent of helium according to the temperature of the gas cooled reactor core under normal working conditions, and performing steady-state calculation until the steady-state calculation reaches convergence to obtain a steady-state pressure field and a speed field of a fuel rod bundle channel as initial values of transient calculation;
Step 4-3: the turbulence model in the transient calculation of the fluid domain adopts a large vortex simulation model, the filtering mode adopts box type filtering, the sub-lattice stress model is selected WALE, the transient calculation is carried out until the residual error of the transient calculation of the fluid reaches the convergence condition of 0.001, and the pressure field of the fluid changing along with the time is obtained through calculation;
Step 5: fluid-solid coupling interface pressure and shear stress distribution analysis: carrying out frequency domain analysis on the value of the fluid exciting force of each time step through a periodogram method to obtain the result of a power spectrum density function of the fluid exciting force, outputting the value of pressure and shearing force of each axial position on the surface of the fuel rod at each moment, and analyzing the influence of the pressure and the shearing force on the positioning of the fuel rod by wire winding;
Step 6: flow induced vibration time domain analysis of the wire-wrapped bundle assembly: loading a pressure field of fluid obtained by fluid domain calculation along with time change on a fluid-solid coupling interface, fixing two axial ends of a fuel assembly, carrying out solid domain calculation, respectively selecting a middle position fuel rod of a rod bundle and one surrounding fuel rod for analysis calculation until finite element calculation of each time step is converged, and obtaining vibration displacement of different points on the surface of the fuel rod at different positions of each time step;
step 7: flow induced vibration frequency domain analysis of the wire winding rod bundle assembly: carrying out frequency domain analysis on vibration displacement of different points on the surface of the fuel rod at different positions of each time step by a periodogram method to obtain a result of a power spectral density function of the vibration displacement;
Step 8: natural frequency analysis of the wire-wrapped bundle assembly: and obtaining the natural frequencies of all orders of the wire-wound rod bundle assembly through prestress modal analysis. And comparing the frequency domain analysis result in the step 7 with the natural frequency result, and analyzing the relation between the vibration of the fuel rod at different positions and the natural frequency.
Preferably, in step 1, the three-dimensional geometry of the obtained flow channel of the bundle assembly with the filament winding is a complete three-dimensional geometry model containing the geometric characteristics of the filament winding, and compared with the prior art, the analysis method provided by the invention can be used for processing the geometric model of the filament winding tangential to the fuel rod and carrying out calculation analysis on the flow field and the solid domain of the fuel rod positioned by the filament winding.
Preferably, in step 2, the fluid domain is meshed by adopting a hexahedral and prismatic layer mixed mesh method, and needs to be pre-calculated by adopting a RANS model, so as to determine the mesh size meeting LES model calculation, compared with the prior art, the method for determining the mesh size required by LES model analysis by adopting a method combining the RANS model and the LES model has the advantages that the mesh determining method is simple and effective, and the flow field calculation adopting the LES model is more accurate
Preferably, because the fluid is helium, the fluid domain calculation selects an implicit solver based on density, monitors mass flow and judges whether the calculation reaches convergence, compared with the prior art, the method aims at the fact that the fluid object is compressible gas, and the convergence speed in solving can be increased by adopting the implicit solver based on density.
Preferably, in the step 3, the solid domain meshing is divided by adopting tetrahedral meshing so as to meet the requirement of solid calculation, and compared with the prior art, the solid domain meshing of the complex structure of the wire-wound fuel rod can be conveniently and rapidly realized by adopting the tetrahedral meshing, so that the calculation of the solid domain is realized.
Preferably, in step 6, the time step of calculating the solid domain is the same as the time step of storing the fluid dynamic calculation output of the fluid domain, so as to ensure that the fluid exciting force is loaded once in each time step. Compared with the prior art, the solid domain analysis time step in the calculation process is the same as the fluid domain analysis time step, and the fluid domain and solid domain results can be conveniently compared and analyzed.

Claims (6)

1. A method for analyzing flow-induced vibration of a gas cooled reactor belt wire-wound fuel rod is characterized by comprising the following steps: the method comprises the following steps:
step 1: modeling a wire winding rod assembly geometric model: modeling according to a fuel rod assembly in a wire winding positioning mode, wherein the modeling comprises a fluid domain and a solid domain, and the three-dimensional geometry of a flow channel with a wire winding rod assembly and the three-dimensional geometry of a wire winding rod assembly structure are obtained;
step 2: the three-dimensional geometry of the flow channel of the filament winding rod bundle assembly is subjected to grid division to meet the requirement of a subsequent large vortex simulation model, namely an LES model, and the method comprises the following specific steps of:
Step 2-1: a fluid domain grid is primarily divided by adopting a polyhedral and prismatic layer mixed grid method so as to meet the requirement that the wall surface y+ is less than 1;
Step 2-2: dividing grids with different sizes, carrying out simulation calculation under the same boundary condition by using the RANS model to carry out grid independence analysis, and determining the minimum grid number meeting calculation;
Step 2-3: using the calculation result of the RANS model to estimate the mesh size satisfying the LES model, the specific formula is as follows:
Δ=max(λ,L/10) (1)
wherein, delta-grid size/m, lambda-Taylor girth scale/m, L-turbulence energy length scale/m; the calculation expressions are respectively:
Wherein, k-turbulence energy/m 2·s-2, v-kinematic viscosity/m 2·s-1, epsilon-energy dissipation rate;
step 2-4: repartitioning the fluid domain mesh according to the estimated mesh size;
step 3: grid division is carried out on the solid domain, namely the three-dimensional geometry of the wire winding rod bundle assembly structure, and grid independence analysis is carried out;
step 4: CFD calculation of the flow channel of the wire-wrapped bundle assembly: the fluid domain calculation is carried out by adopting a computational fluid dynamics method to obtain a pressure field and a speed field of each time step in the transient calculation time period, and the method comprises the following steps:
Step 4-1: inputting an initial speed and an initial pressure of an inlet of a fuel rod bundle channel as steady-state calculation initial values, and adopting a RANS model as a turbulence model of steady-state calculation;
Step 4-2: invoking a helium physical property parameter table, selecting the density, specific heat capacity, thermal conductivity and viscosity of helium according to the temperature of the gas cooled reactor core under the normal working condition, and performing steady-state calculation until the steady-state calculation reaches convergence, so as to obtain a steady-state pressure field and a speed field of a fuel rod bundle channel, and taking the steady-state pressure field and the speed field as initial values of transient calculation;
step 4-3: the turbulence model in the transient calculation of the fluid domain adopts an LES model, a filtering mode adopts box type filtering, a WALE sub-lattice stress model is selected by the sub-lattice stress model, the transient calculation is carried out until the residual error of the transient calculation of the fluid reaches the convergence condition of 0.001, and the pressure field of the fluid changing along with the time is obtained through calculation;
Step 5: fluid-solid coupling interface pressure and shear stress distribution analysis: carrying out frequency domain analysis on the value of the fluid exciting force of each time step through a periodogram method to obtain the result of a power spectrum density function of the fluid exciting force, outputting the value of pressure and shearing force of each axial position on the surface of the fuel rod at each moment, and analyzing the influence of the pressure and the shearing force on the positioning of the fuel rod by wire winding;
Step 6: flow induced vibration time domain analysis of the wire-wrapped bundle assembly: loading a pressure field of fluid obtained by fluid domain calculation along with time change on a fluid-solid coupling interface, fixing two axial ends of a fuel assembly, carrying out solid domain calculation, respectively selecting a middle position fuel rod of a rod bundle and one surrounding fuel rod for analysis calculation until finite element calculation of each time step is converged, and obtaining vibration displacement of different points on the surface of the fuel rod at different positions of each time step;
step 7: flow induced vibration frequency domain analysis of the wire winding rod bundle assembly: carrying out frequency domain analysis on vibration displacement of different points on the surface of the fuel rod at different positions of each time step by a periodogram method to obtain a result of a power spectral density function of the vibration displacement;
Step 8: natural frequency analysis of the wire-wrapped bundle assembly: obtaining the inherent frequencies of all orders of the wire-wound rod bundle assembly through prestress modal analysis; and comparing the frequency domain analysis result in the step 7 with the natural frequency result, and analyzing the relation between the vibration of the fuel rod at different positions and the natural frequency.
2. A method of analyzing flow induced vibrations of a coiled fuel rod for a gas cooled reactor as set forth in claim 1, wherein: in step 1, the three-dimensional geometry of the flow channel of the obtained filament-wound bundle assembly is a complete three-dimensional geometric model containing filament-wound geometric features.
3. A method of analyzing flow induced vibrations of a coiled fuel rod for a gas cooled reactor as set forth in claim 1, wherein: in step 2, the fluid domain is subjected to grid division by adopting a hexahedral and prismatic layer mixed grid method, and a RANS model is required to be adopted for pre-calculation, so that the grid size meeting the LES model calculation is determined.
4. A method of analyzing flow induced vibrations of a coiled fuel rod for a gas cooled reactor as set forth in claim 1, wherein: in step 2, since the fluid is helium, the fluid domain calculation selects an implicit solver based on density, and monitors the mass flow rate to determine if the calculation has reached convergence.
5. A method of analyzing flow induced vibrations of a coiled fuel rod for a gas cooled reactor as set forth in claim 1, wherein: in the step 3, the solid domain grid division is performed by adopting tetrahedral grids so as to meet the requirement of solid calculation.
6. A method of analyzing flow induced vibrations of a coiled fuel rod for a gas cooled reactor as set forth in claim 1, wherein: in the step 6, the time step of calculating the solid domain is the same as the time step of calculating and outputting the stored fluid dynamics of the fluid domain, so that the fluid exciting force is loaded once in each time step.
CN202410459203.0A 2024-04-17 Analysis method for flow-induced vibration of gas cooled reactor belt wire-wound fuel rod Pending CN118246291A (en)

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