The increasingly wide spread use of electronuclear energy has led to t
he need for an improved knowledge of the radiation doses received by v
arious structural materials. Dose rates are particularly high in regio
ns in the vicinity of the core of a reactor, steam generators and the
pool in which spent fuel elements are stored; high dose rates will als
o be encountered at high-level waste disposal sites. In most, involvin
g gamma radiations resulting from the de-activation of fission product
s, thermal conditions can be problematic: temperatures as high as 300-
degrees-C can be reached inside the core or steam generators. Prelimin
ary tests performed in high level waste disposal environments suggest
that similar temperatures are likely to be reached. Thermoluminescence
(TL) dosimetry can be employed if certain conditions are satisfied: t
he TL products must possess at least one deep trap and must also be se
nsitive over a sufficiently wide dynamic range. The following material
s have been investigated for this purpose: dysprosium doped calcium su
lphate powder, alumina and cerium doped ceramic glasses. The maximum d
ose measurable depends on the material employed and ranges from a frac
tion of a kilogray for alumina, to a few kilograys for calcium sulphat
e and cerium doped glasses. A comparative study of the various availab
le products has been performed in order to define the limits and to op
timise their use.