Monitoring fast neutron flux inside spent reactor fuel by CR-39 detector

Authors
Tam, NC Lakosi, L
Citation
Nc. Tam et L. Lakosi, Monitoring fast neutron flux inside spent reactor fuel by CR-39 detector, RADIAT MEAS, 34(1-6), 2001, pp. 601-603
Citations number
7
Categorie Soggetti
Apllied Physucs/Condensed Matter/Materiales Science
Journal title
RADIATION MEASUREMENTS
ISSN journal
13504487 → ACNP
Volume
34
Issue
1-6
Year of publication
2001
Pages
601 - 603
Database
ISI
SICI code
1350-4487(200106)34:1-6<601:MFNFIS>2.0.ZU;2-F
Abstract
A model experiment was carried out by CR-39 detectors using Cf-252 neutron sources in an intense gamma field obtained by Co-60 irradiation. Based on t his calibration and introducing corrections due to the angle, gamma -dose, and etching time dependences of the detector response, fast neutron flux in side spent fuel assemblies was found to be in the range of 10(2)-10(6) n cm (-2) s(-1), depending on burnup and cooling time. The effect of adjacent as semblies can decrease substantially, if the detector surface is perpendicul ar to the axis of the fuel assembly. (C) 2001 Elsevier Science Ltd. All rig hts reserved.