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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
91

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.
92

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.
93

Highly excited states of 12C and 12O from 2He capture studies /

Moon, Kuk Jin January 1969 (has links)
No description available.
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.
95

An investigation of equivalent radii for P₃ calculations in strong absorbers

Noble, Larry Dean. January 1964 (has links)
Call number: LD2668 .T4 1964 N74 / Master of Science
96

Determination of shadowing effects using the P₁ transport model

Porath, William Walter. January 1964 (has links)
Call number: LD2668 .T4 1964 P83 / Master of Science
97

Measurement of the zero power transfer function of the Kansas State University Triga Mark II nuclear reactor

Beeson, Charles Lee. January 1966 (has links)
LD2668 .T4 1966 B415 / Master of Science
98

A study of buoyant backflow in vertical injection lines

King, 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
99

Acoustical boiling detection system for natural convection pool-type reactors

Vidalin, William Edward January 1978 (has links)
No description available.
100

Heat transfer to an accelerated stream of droplets impinging onto a heated surface

Messana, Michael R. 12 1900 (has links)
No description available.

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