Published 1976 | Version v1
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Measurement of radiation-induced heating of uranium in fuel assemblies in the A-1 reactor under operation

Description

The fuel assembly (type E-1, dia 112 mm) is described for the reactor of the first Czechoslovak nuclear power station, with in-core instrumentation involving calorimeters for measuring radiation-induced heating of uranium from which may be determined the neutron flux. In addition to the theoretical background data concerning the measurement itself, the technique of processing the data obtained, as well as the results used for the thermal analysis and evaluation of the reactor's operating safety are presented. (author)

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Additional titles

Subtitle (English)
Program of in-core measurements. Part 4

Publishing Information

Imprint Pagination
17 p.
Report number
ZJE--147