scholarly journals Chemical and spectrochemical production analysis of ThO{sub 2} and {sup 233}UO{sub 2}-ThO{sub 2} pellets for the light water breeder reactor core for Shippingport (LWBR development program)

1975 ◽  
Author(s):  
J. Bukowski ◽  
E. Hollis
Keyword(s):  
Reactor Core ◽  
Development Program ◽  
Light Water ◽  
Production Analysis

Properties of Light Water Reactor Core Melts

1977 ◽  
Vol 32 (3) ◽  
pp. 239-246 ◽  
Author(s):  
S. Nazaré ◽  
G. Ondracek ◽  
B. Schulz
Keyword(s):  
Reactor Core ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor

Chemical Reactions between Light Water Reactor Core Melt and Concrete

1979 ◽  
Vol 46 (2) ◽  
pp. 255-262 ◽  
Author(s):  
Alfred Skokan ◽  
Helmut Holleck ◽  
Martin Peehs
Keyword(s):  
Chemical Reactions ◽  
Reactor Core ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor

A Large-Scale Numerical Simulation on Bubbly and Liquid Film Flows in Narrow Fuel Channels

2005 ◽  
Author(s):  
K. Takase ◽  
H. Yoshida ◽  
Y. Ose ◽  
H. Akimoto
Keyword(s):  
Large Scale ◽  
Two Phase Flow ◽  
Reactor Core ◽  
Light Water Reactor ◽  
Phase Flow ◽  
Analysis Method ◽  
Two Phase ◽  
Light Water ◽  
Water Reactor ◽  
Fuel Bundle

In order to predict the water-vapor two-phase flow structure in a fuel bundle of an advanced light-water reactor, large-scale numerical simulations were carried out using a newly developed two-phase flow analysis method and a highly parallel-vector supercomputer. Conventional analysis methods such as subchannel codes need composition equations based on many experimental data. Therefore, it is difficult to obtain highly prediction accuracy on the thermal design of the advanced light-water reactor core if the experimental data are insufficient. Then, a new analysis method using the large-scale direct numerical simulation of water-vapor two-phase flow was proposed. The coalescence and fragmentation of small bubbles were investigated numerically and the bubbly flow dynamics in narrow fuel channels were clarified. Moreover, the liquid film flow inside a tight-lattice fuel bundle which is used to the advanced light-water reactor core was analyzed and the water and vapor distributions around fuel rods and a spacer were estimated quantitatively.

Investigation of Activity Release During Light Water Reactor Core Meltdown

1978 ◽  
Vol 40 (3) ◽  
pp. 278-283 ◽  
Author(s):  
H. Albrecht ◽  
V. Matschoss ◽  
H. Wild
Keyword(s):  
Reactor Core ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor ◽  
Core Meltdown
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