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Experimental and mathematical simulation techniques for determining an in-situ response testing method for neutron sensors used in reactor power plant protection systems /Behbahani, Alireza January 1983 (has links)
No description available.
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The numerical solution of the space-time reactor kinetics equations using an alternating direction explicit procedure /Iyer, Shrinivas Shankar January 1969 (has links)
No description available.
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93 |
Highly excited states of 12C and 12O from 2He capture studies /Moon, Kuk Jin January 1969 (has links)
No description available.
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94 |
Some autocatalytic effects during explosive power transients in liquid metal cooled, fast breeder, nuclear reactors (LMFBRs) /Webb, Richard E. January 1972 (has links)
No description available.
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95 |
An investigation of equivalent radii for P₃ calculations in strong absorbersNoble, Larry Dean. January 1964 (has links)
Call number: LD2668 .T4 1964 N74 / Master of Science
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Determination of shadowing effects using the P₁ transport modelPorath, William Walter. January 1964 (has links)
Call number: LD2668 .T4 1964 P83 / Master of Science
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Measurement of the zero power transfer function of the Kansas State University Triga Mark II nuclear reactorBeeson, Charles Lee. January 1966 (has links)
LD2668 .T4 1966 B415 / Master of Science
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A study of buoyant backflow in vertical injection linesKing, John Barry 01 May 1991 (has links)
In the event of a small break loss of coolant accident
(SBLOCA) in a nuclear reactor, cold fluid is injected through
the reactor system high pressure injector to compensate for
the coolant loss. When this flow rate is less than a critical
value, however, the hot fluid in the cold leg penetrates into
the vertical injection line in a process called buoyant
backflow. Because the resulting penetrations induce thermal
stresses in the pipe, the presence of backflow in the
injection lines is potentially significant.
Since these penetrations could potentially damage the
pipe, it was the purpose of this study to evaluate the
backflow behavior. To this end, both the critical injection
conditions and the subcritical penetration depth were
experimentally determined through flow simulation in a 1/5
scale model. In addition, the experimental trends wi-re
modeled theoretically. By matching the theoretical results to
the experimental data, it was determined that backflow began
below a critical Froude number of .65 and increased in depth
with the negative logarithm of the injection velocity. The
agreement between theory and experiment was excellent.
For a certain class of reactor systems, the full scale
Froude numbers were then compared to the critical value
obtained in the analysis. For the systems involved in this
comparison, the full scale Froude numbers were shown to be
less than .65 for all practical flow rates. As a consequence,
buoyant backflow is expected within the injection lines of
these reactors, under safety injection conditions. / Graduation date: 1991
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Acoustical boiling detection system for natural convection pool-type reactorsVidalin, William Edward January 1978 (has links)
No description available.
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100 |
Heat transfer to an accelerated stream of droplets impinging onto a heated surfaceMessana, Michael R. 12 1900 (has links)
No description available.
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