scholarly journals EXPERIMENTAL STUDIES OF THE HEAT TRANSFER AND FLUID DYNAMIC CHARACTERISTICS OF ROD-CLUSTER-TYPE NUCLEAR REACTOR FUEL ELEMENTS.

1970 ◽  
Author(s):  
H.W. Hoffman ◽  
G.J. Jr. Kidd ◽  
F.E. Lynch ◽  
W.J. Stelzman ◽  
J.L. Wantland ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Dynamic Characteristics ◽  
Nuclear Reactor ◽  
Fluid Dynamic ◽  
Experimental Studies ◽  
Reactor Fuel ◽  
Nuclear Reactor Fuel ◽  
Cluster Type ◽  
Fuel Elements

Heat-Transfer and Flow-Friction Characteristics of Crossed-Rod Matrices

1960 ◽  
Vol 82 (3) ◽  
pp. 199-213 ◽  
Author(s):  
A. L. London ◽  
J. W. Mitchell ◽  
W. A. Sutherland
Keyword(s):  
Heat Transfer ◽  
Electrical Resistance ◽  
Heat Exchangers ◽  
Air Conditioning ◽  
Nuclear Reactor ◽  
Heat Transfer Surface ◽  
Friction Behavior ◽  
Flow Friction ◽  
Nuclear Reactor Fuel ◽  
Fuel Elements

The paper presents a continuation of the program on porous media heat-transfer and flow-friction behavior previously covered in References [2b] and [3b]. All the previous results of interest to the designer on woven-screen matrices and crossed-rod matrices of a random configuration are summarized here. In addition, new design results for the regular in-line and regular staggered crossed-rod-matrix configurations are reported. Matrices of the type considered here may find application as heat-transfer surface geometries for nuclear-reactor fuel elements, for electrical resistance heaters and for periodic-flow-type heat exchangers used for gas-turbine regenerators, and some air-conditioning applications.

Enlarged radiochemical equipment using the radiation from spent nuclear reactor fuel elements

1963 ◽  
Vol 15 (4) ◽  
pp. 1018-1024 ◽  
Author(s):  
V. L. Karpov ◽  
A. Kh. Breger ◽  
M. E. Eroshov ◽  
V. E. Drozdov ◽  
G. N. Lisov ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Reactor Fuel ◽  
Nuclear Reactor Fuel ◽  
Fuel Elements
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