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.Files
11513764.pdf
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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.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11513764
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL RODS; PERFORMANCE TESTING; POWER-COOLING-MISMATCH ACCIDEN; PWR TYPE REACTORS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; FUEL ELEMENTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; TESTING; WATER COOLED REACTORS; WATER MODERATED REACTORS