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Area Monitoring Dosimeters - doe-std-1098-99_reaffirmed_2004_120117
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Radiological Control - index
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Part 2 Internal Dosimetry - doe-std-1098-99_reaffirmed_2004_120119


DOE-STD-1098-99
Radiological Control
Radiological Health Support Operations
June 2004
1.
Facilities that possess fissile materials in sufficient quantities to create a critical mass such that the potential exists
for excessive exposure of individuals in an accident shall provide nuclear accident dosimetry to affected individuals
[see 835.1304(a)].
2.
The nuclear accident dosimetry system shall include the following:
a.
A method to conduct initial screening of potentially exposed individuals to identify those who have received
significant doses [see 835.1304(b)(1)]
b.
Equipment and methods sufficient to analyze appropriate biological samples [see 835.1304(b)(2)] and
dosimeters
c.
A system of fixed nuclear accident dosimeter units [see 835.1304(b)(3)] capable of measuring the estimated
neutron dose and approximate neutron spectrum
d.
Personnel nuclear accident dosimeters [see 835.1304(b)(4)] .
3.
The fixed dosimeters discussed above should:
a.
Be capable of determining the neutron dose from 10 rads to approximately 10,000 rads with an accuracy of
25%
b.
Be capable of measuring fission gamma radiation from 10 rads to approximately 10,000 rads in the presence
of neutron radiation with an accuracy of approximately 25%.
4.
Personnel nuclear accident dosimeters should be capable of measuring an absorbed dose in or on a phantom from
10 rads to approximately 1,000 rads with an accuracy of 25%.
5.
An analysis of the fixed dosimetry system needs should be documented and should consider such factors as the
nature of operations, structural design of the facility, area accessibility, number of dosimeters and their location,
and the effect of intervening shielding. The analysis should be reevaluated as necessary to ensure facility
modifications do not impair the capabilities of the fixed dosimetry system.
5-6


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