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Abstract

The main objective of this review is to provide the neutron relative sensitivity for TL materials which may be used for assessing the gamma-ray dose in mixed neutron - gamma fields. TL materials considered include Al-2O-3, BeO, CaF-2, CaSO-4, Li-2B-4O-7, natural LiF, 6-LiF, 7-LiF, MgB-4O-7 and Mg-2SiO-4.

Additional information

Authors: GIBSON J A B ENVIRONMENTAL AND MEDICAL SCIENCES DIVISION, AERE, HARWELL (UK), ENVIRONMENTAL AND MEDICAL SCIENCES DIVISION, AERE, HARWELL (UK)
Bibliographic Reference: EUR 10105 EN (1985) FS, 79 P., BFR 300, EUROFFICE, LUXEMBOURG, POB 1003
Availability: Can be ordered online
Record Number: 1989124051200 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en