Numerical investigation of temperature fields in the duct of uranium-graphite reactor with fuel elements of bush type

2006 ◽  
Vol 13 (3) ◽  
pp. 419-425
Author(s):  
A. N. Cherepanov ◽  
V. N. Popov ◽  
A. E. Detsel ◽  
A. B. Aleksandrov ◽  
A. I. Drobyaz
Keyword(s):  
Numerical Investigation ◽  
Temperature Fields ◽  
Graphite Reactor ◽  
Fuel Elements

Numerical Investigation of Flow and Heat Transfer Performance of Nano-Encapsulated Phase Change Material Slurry in Microchannels

2009 ◽  
Vol 131 (6) ◽  
Author(s):  
Sarada Kuravi ◽  
Krishna M. Kota ◽  
Jianhua Du ◽  
Louis C. Chow
Keyword(s):  
Heat Transfer ◽  
Phase Change ◽  
Numerical Investigation ◽  
Phase Change Material ◽  
Temperature Fields ◽  
Heat Transfer Fluid ◽  
Inlet Temperature ◽  
Bulk Fluid ◽  
Encapsulated Phase Change Material ◽  
Change Material

Microchannels are used in applications where large amount of heat is produced. Phase change material (PCM) slurries can be used as a heat transfer fluid in microchannels as they provide increased heat capacity during the melting of phase change material. For the present numerical investigation, performance of a nano-encapsulated phase change material slurry in a manifold microchannel heat sink was analyzed. The slurry was modeled as a bulk fluid with varying specific heat. The temperature field inside the channel wall is solved three dimensionally and is coupled with the three dimensional velocity and temperature fields of the fluid. The model includes the microchannel fin or wall effect, axial conduction along the length of the channel, developing flow of the fluid and not all these features were included in previous numerical investigations. Influence of parameters such as particle concentration, inlet temperature, melting range of the PCM, and heat flux is investigated, and the results are compared with the pure single phase fluid.

scholarly journals EXPERIMENTAL STUDIES ON DEVELOPMENT OF THE METHOD FOR DETERMINING THE AMOUNT OF IMPURITATED GASES IN NUCLEAR FUEL

2022 ◽  
pp. 29-36
Author(s):  
G. A. Vityuk ◽  
V. A. Vityuk ◽  
A. D. Vurim ◽  
R. Y. Kelcingazina ◽  
B. Y. Bekmagambetova
Keyword(s):  
Nuclear Fuel ◽  
Total Pressure ◽  
Experimental Studies ◽  
Severe Accident ◽  
Neutron Pulse ◽  
Graphite Reactor ◽  
Fuel Elements

The article is devoted to an issue of estimating the impurity gas amount in nuclear fuel in the aspect of the distracting contribution from released gases to the total pressure inside ampoule of the device in the simulating a severe accident with core melting. The paper presents a method based on measuring the pressure and temperature of gas in a closed values of the fuel elements during the fuel melting. The correctness of the developed methodology is confirmed by the results of experiments on the melting of fuel in a pulsed graphite reactor IGR with the implementation of a controlled neutron pulse.

Numerical Investigation of Natural Convection in a Square Enclosure with a Baffle Mounted on Vertical Wall

2015 ◽  
Vol 813-814 ◽  
pp. 748-753 ◽  
Author(s):  
N. Nagasubramanian ◽  
M.R. Thansekhar ◽  
M. Venkatesan ◽  
K. Ramanathan
Keyword(s):  
Natural Convection ◽  
Numerical Investigation ◽  
Average Nusselt Number ◽  
Vertical Wall ◽  
Temperature Fields ◽  
Cold Wall ◽  
Primary Vortex ◽  
Square Enclosure ◽  
Flow And Heat Transfer ◽  
Laminar Natural Convection

Results from numerical investigation of laminar natural convection inside a differentially heated square enclosure with a thin baffle attached to the cold wall are reported. The effect of the baffles on the flow and temperature fields were analyzed for baffle lengths equal to 20, 35 and 50 percent of the width of the enclosure, attached at three locations for Ra = 104, 105, 106 and Pr = 0.707. The presence of a baffle on the cold right wall affects the strength of the clockwise rotating primary vortex. Reduced flow and heat transfer are observed. Longer the baffle more pronounced the effect on the flow field. Secondary convection cells are seen between the baffle and the bottom wall for certain cases. Reduction in average Nusselt Number is observed on the cold wall with the baffle than the hot wall.

Investigation of temperature fields in fast reactor fuel elements with variable power distribution over height of core

1970 ◽  
Vol 28 (6) ◽  
pp. 621-621
Author(s):  
V. F. Dobrovol'skii ◽  
A. V. Zhukov ◽  
E. Ya. Sviridenko ◽  
V. I. Subbotin ◽  
P. A. Ushakov
Keyword(s):  
Fast Reactor ◽  
Power Distribution ◽  
Reactor Fuel ◽  
Temperature Fields ◽  
Fast Reactor Fuel ◽  
Variable Power ◽  
Fuel Elements

Temperature fields of fuel elements in the bor reactor core

1970 ◽  
Vol 28 (6) ◽  
pp. 620-621
Author(s):  
V. I. Subbotin ◽  
P. A. Ushakov ◽  
A. V. Zhukov ◽  
E. Ya. Sviridenko
Keyword(s):  
Reactor Core ◽  
Temperature Fields ◽  
Fuel Elements

Numerical Investigation of the Plain-Strain Compression of a Spherical Shell

2014 ◽  
Vol 611-612 ◽  
pp. 1617-1626
Author(s):  
Michael A. Petrov ◽  
Pavel A. Petrov
Keyword(s):  
Numerical Investigation ◽  
Energy Efficient ◽  
Elevated Temperatures ◽  
Hollow Spheres ◽  
Solid Material ◽  
Inert Gas ◽  
Temperature Fields ◽  
Theoretical Assumption ◽  
Deformation Force ◽  
Plain Strain

The present paper reveals one of the energy efficient ways of science investigation of materials for light construction purposes. The small hollow spheres made from different materials could change the weight of a construction part essentially, used as acoustic and thermal insulation and also as protection against vibrations. They can be used as a unit cell for big parts and alone filled with an inert gas, e.g. fusion targets. Pure tin shells were produced in transient (thixotropic) state of materials at elevated temperatures (close to the melting point of the pure tin melt) and several simulation steps were used, to determine the preferable boundary conditions. To one of them belongs the investigation of the temperature fields during the formation process. The formation force was determined theoretically. Also a theoretical assumption, that the solid material needs the same deformation force value or close to it, the numerical investigation was also carried out in FE-code QForm-3D.

Start-up and operation of channel-type uranium-graphite reactor with tubular fuel elements and nuclear steam superheating

1971 ◽  
Vol 30 (2) ◽  
pp. 163-170 ◽  
Author(s):  
P. I. Aleshchenkov ◽  
G. A. Zvereva ◽  
G. A. Kireev ◽  
G. D. Knyazeva ◽  
V. I. Kononov ◽  
...  
Keyword(s):  
Graphite Reactor ◽  
Start Up ◽  
Tubular Fuel ◽  
Fuel Elements ◽  
Steam Superheating ◽  
Channel Type

A Numerical Investigation on Nanofluid Laminar Mixed Convection in Confined Impinging Jets

2013 ◽  
Author(s):  
O. Manca ◽  
S. Nardini ◽  
D. Ricci ◽  
S. Tamburrino
Keyword(s):  
Nusselt Number ◽  
Numerical Investigation ◽  
Stream Function ◽  
Local Nusselt Number ◽  
Richardson Number ◽  
Convective Heat Transfer Coefficient ◽  
Temperature Fields ◽  
Bulk Temperature ◽  
Al2o3 Nanoparticles ◽  
Laminar Mixed Convection

In this paper a numerical investigation on confined impinging slot jets working with a mixture of water and Al2O3 nanoparticles is described. The flow is laminar and a constant temperature is applied on the target surface. A single-phase model approach has been adopted because the particle concentrations are low. Different geometric ratios and nanoparticle volume concentrations have been considered at different Richardson numbers in order to take into account also the buoyancy effects. The aim consists into study the behaviour of the system by means of average and local Nusselt number, convective heat transfer coefficient and required pumping power profiles, temperature fields and stream function contours. The dimensionless stream function contours showed that the intensity and size of the vortex structures depend on the confining effects, given by H/W ratio, Richardson number and particle concentrations. Furthermore, for increasing concentrations, nanofluids realize increasing fluid bulk temperature, as a result of the elevated thermal conductivity of mixtures. The local Nusselt number profiles show the highest values at the stagnation point and they depend on Richardson number and particle concentrations.

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