Published 1979 | Version v1
Report Open

Measurement of fission product release during LWR fuel failure

Description

The PBF is a specialized test reactor consisting of an annular core and a central test space 21 cm in diameter and 91 cm high. A test loop circulates coolant through the central experimental section at typical power reactor conditions. Light-water-reactor-type fuel rods are exposed to power bursts simulating reactivity insertion transients, and to power-cooling-mismatch conditions during which the rods are allowed to operate in film boiling. Fission product concentrations in the test loop coolant are continuously monitored during these transients by a Ge(Li) detector based gamma spectrometer. Automatic batch processing of pulse height spectra results in a list of radionuclide concentrations present in the loop coolant as a function of time during the test. Fission product behavior is then correlated to test parameters and posttest examination of the fuel rods. Data are presented from Test PCM-1

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.

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Additional details

Publishing Information

Imprint Pagination
7 p.
Report number
CONF-790935--2

Conference

Title
IAEA specialists meeting on defected zirconium alloy clad ceramic fuel in water cooled reactors.
Dates
17 - 21 Sep 1979.
Place
Chalk River, Canada.