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Indirect or In Vitro Measurement - doe-hdbk-1113-98_reaffirm_2005_040077
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Radiological Safety Trainign for Uranium Facilities
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Contamination Control Philosophy - doe-hdbk-1113-98_reaffirm_2005_040079


DOE-HDBK-1113-98
Module 104 Internal Dose Control
Lesson Plan
Instructor's Notes
Alpha and beta radiation emitted by material
inside the body is shielded by body tissue and
cannot be detected.
Direct measurement is useful for detecting
uranium that is not easily eliminated by the
body. This method may also be used to estimate
an internal dose. Because of the very low energy
and intensity of gamma radiation emitted from
depleted uranium, direct measurements are not
effective in detecting depleted uranium in the
body.
D.
Internal Dose Reduction and Control Techniques
The hierarchy for minimization of internal dose is
given in the RCS, Article 316. Engineering controls
should be the primary method of minimizing
airborne contamination and internal exposure to
workers, where practicable. Administrative controls,
including access controls and specific work
practices, should be used as the secondary method to
minimize internal exposure. If the potential for
airborne radioactivity still exists after engineering
and administrative controls have been applied,
respiratory protection should be considered. Other
specific controls, such as stay times, worker safety,
comfort, and efficiency, are also discussed in Article
316.
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