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Numerical simulation of transient heat transfer in a pulsed reactor fuel pinWeaver, Peter David, 1948- January 1977 (has links)
No description available.
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Critical heat flux for a heated surface impacted by a stream of liquid dropletsCarson, Robert J. 12 1900 (has links)
No description available.
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An experimental investigation of acoustic cavitation as a fragmentation mechanism of molten tin droplets in water.Bjørnard, Trond Arnold January 1976 (has links)
Thesis. 1976. M.S. cn--Massachusetts Institute of Technology. Dept. of Nuclear Engineering. / MICROFICHE COPY AVAILABLE IN ARCHIVES AND SCIENCE. / Includes bibliographical references. / M.S.cn
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A thermal-hydraulic analysis of the cooling system for the 500 KW Virginia Polytechnic Institute and State University reactorLo, Ai-Tai January 1982 (has links)
In order to increase the usefulness of the nuclear research reactor, it is necessary to enhance the neutron fluxes available in the experimental facilities. One method of attaining this objective is to increase the power level of the reactor.
The VPI&SU 100 KW research reactor has been studied to investigate the feasibility of operation of 500 KW. From a thermal-hydraulic point of view, the following limiting conditions should not be exceeded for a 500 KW operation:
1) bulk boiling of the coolant should not occur,
2) surface boiling should not occur on any fuel plate,
3) fuel meltdown must not occur after a loss-of-flow or loss-of-coolant accident,
4) fuel plate vibration problems should not be significant.
The results of the investigation indicate that the above limiting conditions will not be exceeded provided that certain system modifications are made. Thus the operation of the VPI&SU reactor at 500 KW is feasible as far as thermal-hydraulics is concerned. / 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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The hydrodynamics of countercurrent two-phase flow in inclined channelsTurk, Rodney Eric 12 1900 (has links)
No description available.
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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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Modeling of once-through steam generator thermal-hydraulics during a loss of coolant accidentKamboj, Brij Kumar 05 1900 (has links)
No description available.
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An analysis of mono-dispersed liquid droplet coolingHausgen, Paul E. 12 1900 (has links)
No description available.
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The effect of countercurrent flow limitation in small passagesBohner, John David 12 1900 (has links)
No description available.
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