HEAT TRANSFER IN NUCLEAR REACTOR SAFETY. International Seminar 1980

Author(s):  
S. George Bankoff
1976 ◽  
Vol 190 (1) ◽  
pp. 215-224
Author(s):  
W. B. Hall

Reactor safety assessment is a highly specialized topic which, in many of its aspects, depends heavily on a satisfactory understanding of a wide variety of heat transfer phenomena. It is the aim of the paper to air some of these problems outside the ranks of the reactor safety specialists. Typical liquid-cooled reactors, their operating characteristics, and some heat transfer aspects of their safety assessment are discussed: for example, transient boiling, quenching of hot surfaces and thermal explosions.


1982 ◽  
Vol 104 (1) ◽  
pp. 48-54 ◽  
Author(s):  
R. A. Nelson

Mechanisms in the postcritical heat flux region that provide understanding and qualitative prediction capability for several current force-convective heat-transfer problems are discussed. In the area of nuclear reactor safety, the mechanisms are important in the prediction of fuel rod cooldown and quenches for the reflood phase, blowdown phase, and possibly some operational transients with dryout. Results using the mechanisms to investigate forced-convective quenching are presented. Data reduction of quenching experiments is discussed, and the way in which the quenching transient may affect the results of different types of quenching experiments is investigated. This investigation provides an explanation of how minimum wall superheats greater than the homogeneous nucleation temperature result, as well as how these may be either hydrodynamically or thermodynamically controlled.


1982 ◽  
Vol 58 (1) ◽  
pp. 122-123
Author(s):  
Clifford J. Cremers

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