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DOE-STD-1136-2004
Guide of Good Practices for Occupational Radiation Protection in Uranium Facilities
method is less sensitive than the use of indium foils and even a small reading can indicate a significant
exposure. An approximate equation to calculate worker dose (D) based on body weight and instrument
reading is shown in Equation 7.1:
(7.1)
Differences in incident neutron energy spectrum, orientation, and measurement techniques relative
to conditions used to develop activity-dose correlations can cause significant errors in estimated radiation
dose based on quick-sort surveys. Swaja and Oyan showed radiation doses estimated from induced body
activity can vary by a factor of approximately 2 because of neutron energy spectrum or orientation effects
and by as much as 30% due to probe position. Doses based on indium foil activity can vary by a factor of
approximately 9 due to neutron energy spectrum effects, a factor of 3 depending on foil orientation relative
to the incident field, and a factor of approximately 2 due to probe window setting. Swaja and Oyan
recommended those count rates above background during quick-sort techniques should be initially
interpreted only as an indication that the person has been exposed.
7.4.2.2 Fixed and Personnel Nuclear Accident Dosimeters
A comprehensive nuclear criticality dosimetry system should consist of stationary (fixed- location,
area) dosimeters, neutron and gamma dosimeters worn by personnel (i.e., PNADs), and specialized
laboratory equipment to evaluate the dosimeters.
Fixed nuclear accident dosimeter units should be capable of determining neutron doses in the range of
10 rad to 10,000 rad with an accuracy of 25%. They should also be capable of providing the approximate
neutron spectrum to permit the conversion of rad to rem. The gamma-measuring component of the
dosimeter should be capable of measuring doses in the range of 10 rem to 10,000 rem in the presence of
neutrons with an accuracy of about 20%. The number of fixed dosimeter units needed and their
placement will depend on the nature of the operation, structural design of the facility, and accessibility of
areas to personnel. Generally, dosimeters should be placed so there is as little intervening shielding and as
few obstructions as possible. The number and placement of dosimeters should be periodic ally reverified to
reflect changes in building design and operations. Ease of dosimeter recovery after a criticality event
should be considered in their placement, including the possible need for remote retrieval.
PNADs should be worn by all individuals who enter a controlled area, with locations requiring an
installed criticality alarm system. The PNADs should be capable of determining gamma dose from
10 rad to 1000 rad with an accuracy of 20% and neutron dose from 1 rad to 1000 rad with an accuracy of
30% without dependence upon fixed-unit data.
The general criteria of ANSI N13.3 for nuclear accident dosimeters are reviewed below.
Dosimeters, both fixed and personnel, should be protected against radioactive contamination to avoid
false measurements. Periodic inventory methods should be established and audits made to ensure the
dosimeters are not removed or relocated without appropriate approvals. Techniques for estimating the
effect of body orientation at the time of the exposure should also be developed.
Neutron-Measuring Component of Dosimeter.Criticality accidents create a wide range of neutron
energies. Since the neutron dose per unit fluence is strongly dependent on neutron
7-10


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