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Sugiyama, Tomoyuki; Fuketa, Toyoshi
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
AbstractAbstract
[en] In order to clarify fuel behavior under reactivity initiated accident (RIA) conditions, pulse irradiation experiments on fuel rods are carried out in the Nuclear Safety Research Reactor (NSRR). One of concerns at fuel failure is mechanical energy generation in the reactor vessel. The mechanical energy is generated by a water hammer or a pressure impact occurred at fuel failure, and has possibility to damage reactor structures. Thus, the amount of generated mechanical energy is critical information for the safety evaluation of power reactor. In the NSRR experiments, the mechanical energy due to the water hammer is evaluated as the kinetic energy of the jumping water column at fuel failure, and the velocity of the water column is measured by the float type water column velocimeter. This report presents characteristics of the water column velocimeter and the procedure of data processing in the NSRR experiments. (author)
Primary Subject
Source
Nov 2000; 36 p; 6 refs., 21 figs.
Record Type
Report
Report Number
Country of publication
ACCIDENTS, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, HYDROGEN COMPOUNDS, IRRADIATION, MEASURING INSTRUMENTS, MECHANICS, MIXED SPECTRUM REACTORS, OXYGEN COMPOUNDS, PROCESSING, PULSED REACTORS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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