APPLICATION OF CR-39 DETECTORS IN SPENT REACTOR-FUEL ASSAY

Citation
Nc. Tam et al., APPLICATION OF CR-39 DETECTORS IN SPENT REACTOR-FUEL ASSAY, Radiation measurements, 28(1-6), 1997, pp. 781-784
Citations number
4
Journal title
ISSN journal
13504487
Volume
28
Issue
1-6
Year of publication
1997
Pages
781 - 784
Database
ISI
SICI code
1350-4487(1997)28:1-6<781:AOCDIS>2.0.ZU;2-U
Abstract
Fast neutrons from reactor fuel were monitored with CR-39 track detect ors, using energy discrimination by shape selection to reduce the numb er of disturbing events. The detectors were irradiated in a steel cont ainer placed on the top of assemblies. Exposure time was optimized for providing acceptable statistics and keeping gamma-dose low enough bel ow 6 kGy - to prevent the material from damage due to the huge intensi ty gamma-background. As the effect of the adjacent assemblies in a hex agonal lattice of 160 mm storage distance is rather high, individual a ssay on isolated fuel assemblies is recommendable.