Abstract
High-temperature bent heat pipes are safety-level heat transfer components used in heat pipe cooled reactor, and their applications are becoming increasingly widespread. In this study, a comprehensive three-dimensional numerical model was established to evaluate the effects of different bending angles and radii on the performance of high-temperature heat pipes. The model solved for the temperature, pressure, and velocity fields in the wall, wick, and evaporator, considers the compressibility effect of the vapor. The study investigated parameters such as vapor pressure, vapor velocity, radial secondary flow field, wall temperature, wick temperature, and equivalent thermal resistance of powder sintered core sodium heat pipes with bending angles of 45°, 90°, 135°, 180°, and a bending radius under 90°. The results showed that when sodium vapor enters the bent pipe, the vapor flow deviates towards the outer side, resulting in higher vapor pressure at the outer side than the vapor pressure at the inner side, and the generation of radial secondary vortex. This leads to higher temperature in the evaporator and adiabatic sections of the bent heat pipe, while lower temperature in the condenser. Fractal patterns are observed in the outer and inner wall temperature curve in the adiabatic section, with lower temperatures on the inner side and higher temperatures on the outer side. The bent heat pipe exhibits higher equivalent thermal resistance than that of a straight heat pipe, and the equivalent thermal resistance increases with increasing bending angle, and the equivalent thermal resistance decreases with increasing bending radius.
Funding source: Anhui Provincial Key Research and Development Project
Award Identifier / Grant number: No. 2022107020018
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission. Xiongwei Cheng: Writing – original draft, Validation, Investigation, Formal analysis. Hualei Jiang: Writing – review & editing, Investigation. Taosheng Li: Supervision, Conceptualization. Siwei Zhang: Writing – review & editing, Resources, Conceptualization. Chengjun Duan: Writing – review & editing, Investigation. Huaping Mei: Funding acquisition.
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Competing interests: The authors state no conflict of interest.
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Research funding: This work is supported by Anhui Provincial Key Research and Development Project (No. 2022107020018).
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Data availability: The raw data can be obtained on request from the corresponding author.
Nomenclature
- C p
-
specific heat (J/kg K)
- h fg
-
latent heat of vaporization (kJ/kg)
- k
-
thermal conductivity (W/m K)
- K
-
permeability (m2)
- L
-
length (m)
- P
-
pressure (Pa)
- Q
-
heat transfer (W)
- R g
-
gas constant (J/[mol K])
- T
-
temperature (k)
- V
-
velocity vector
- μ
-
dynamic viscosity (kg/m s)
- ρ
-
density, (kg/m3)
- n
-
unit normal vector
- u
-
Velocity(m/s)
- ε
-
wick porosity
- Q evap
-
heat transfer of evaporator (W)
- h f
-
convective heat transfer coefficient(W/m2 k)
- σ
-
Stefan-Boltzmann constant (W/[m2 K4])
- ω
-
spectral emissivity
- r p
-
radius of outer wall (m)
- l e
-
length of evaporator (m)
- M
-
Molar mass (g/mol)
Subscripts
- eff
-
effective
- w
-
wick
- v
-
vapor
- l
-
liquid
- ref
-
reference
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Articles in the same Issue
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events
Articles in the same Issue
- Frontmatter
- Numerical study on the effect of the PI-controller type on the quasi-steady reactor pressure in MAAP 5.04 code
- Analyses of the unavailability dynamics of emergency core cooling system
- Study on spent fuel heatup during spent fuel pool complete loss of coolant accident
- Numerical simulation analysis of high-temperature bent sodium heat pipes
- Influence of the twisting and nano fluids on performance of a triangular double tube heat exchanger
- Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
- Gain scheduled internal model control based on the dynamic sliding mode method for the water level of nuclear steam generators
- Verification and validation optimization method for signal quality bits in digital control system application software of nuclear power plant
- Investigation of Li–Be and B halides as blanket in future fusion molten salt reactor
- A study on porosity investigation of compacted bentonite in various densities by using micro-computed tomography images analysis
- CTAB modification bentonite for enhanced Re adsorption and diffusion suppression
- Study on advection–dispersion behavior for simulation of 3H, 99Tc, and 90Sr transport in crushed sandstone of column experiments
- Investigating advection–dispersion behavior for simulation of HTO and 238Pu transport in argillaceous shale with different varying degrees of weathering
- Study on analysing the potential benefits of utilizing nuclear waste for biodiesel production
- Calendar of events