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This was done in this laboratory
by oslculating the millirem output of the
neutrons that is to say, eslculating the

number of millireps, the number of neutrons

required to produce a millirep and then using

the Tissue Equivalent Chamber with a atanderd
radium source encapsulated in a half a milli-~meter of platinum,
The unaccounted dose
rate was attributed to the gamma dose rate
of the source.

All our measurements are reported

with the lonizetion ehamber in terms of the
polonium beryllium equivslent flux, This
flux is not necessarily the same as the

flux, the actual fiux in the region,

It

would rerély be the soase except under rare
conditions among which would be the case

of the stray radiation, energy spectrum
which was the same ag that of polonium
berylliuns,

However, the ratio of a flux to

a permissible flux at a given energy is *
strictly proportional to the dose rate,

Under ordinary use, we uce the
Graphite and the BFs Chambers to evaluate

the neutron and gamma dose rates,
These
are converted to millirem per hour and then

Select target paragraph3