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DOE-STD-1128-98
Guide of Good Practices for Occupational Radiological Protection in Plutonium Facilities
It is not generally well known that neutron survey instruments have a severe energy
dependence. In fact, some manufacturers claim a 15% response per unit dose
equivalent extending over an energy range of thermal to 15 MeV. The energy
dependence of several commercially available neutron survey meters has been
experimentally measured at the PTB in Germany (Liesecki and Cosack, 1984). Their
measurements made with monoenergetic neutrons in low-scatter conditions demonstrate
that a typical moderator-based neutron survey meter underestimates the dose equivalent
by a factor of 2 at an energy of 14 MeV and overestimates dose equivalent by a factor of
2 to 3 at an energy of 20 keV. Survey instruments also exhibit changes in response with
the direction of incidence of the neutrons due to absorption and scattering of the neutrons
by the electronics package attached to the moderator/detector. This can also result in
40% variation in response, depending on the direction of incidence. Fortunately,
plutonium compounds emit neutrons in the MeV range, where the problems with energy
and angular responses are minimal. Accuracies of 15% can be achieved with careful
calibration with 252Cf or other fission sources.
6.3.2
Personnel Dosimetry
The detailed requirements of an external dosimetry program are given in the
Implementation Guide. External Dosimetry Program (DOE, 1999e). Explicit guidance
and requirements are given and need not be repeated here. This section will focus on
dosimetry problem areas specific to plutonium facilities and possible solutions.
Personnel working in plutonium facilities are exposed to both photon and neutron
radiations, and plutonium processing is one of the largest contributors to neutron
exposure in the United States. The response of beta-gamma personnel dosimeters is well
documented and will not be discussed here.
The response of neutron dosimeters to the neutron fields encountered in the workplace
must be evaluated. All existing neutron dosimeters have a severe energy response
problem and must be carefully calibrated for the specific radiation field in which the
neutron dosimeter is worn. Typically, neutron dosimeters are calibrated to either bare
252
Cf or D2O-moderated 252Cf sources in a low-scatter calibration facility. Then, the
neutron dosimeters are worn in plutonium facilities under high-neutron-scatter
conditions, which produce a completely different energy spectrum than that in which the
dosimeter was calibrated. Accordingly, a typical approach is to perform neutron energy
field characterization surveys at selected areas in a facility. Based on these surveys a
field correction factor is determined which corrects for the difference between the
dosimeter response to the calibration source and the response to the neutron fields in the
workplace. Because of the large response of TLD-albedo dosimeters to low-energy
neutrons (with energies below about 20 keV), the response of the dosimeter usually
6-20


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