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A. RADIATION PROTECTION STANDARDS
TEDE
= TOTAL EFFECTIVE DOSE EQUIVALENT ALARA
PHILOSOPHY Current
scientific evidence concedes that there may not be a risk-free level of
radiation exposure. Therefore,
in addition to providing an upper limit on a person's permissible
radiation exposure, the NRC also requires that its licensees maintain
occupational exposures as low as reasonably achievable
(ALARA). This means that
every activity involving exposure to radiation should be planned so as to
minimize unnecessary exposure to individual workers and the worker
population. All experimental
procedures should be reviewed with the objective of reducing unnecessary
exposures. An
ALARA program has been incorporated as part of the University’s NRC
license. It outlines the
responsibilities of several groups. Management
has the responsibility to provide an administrative organization and the
resources to operate it. The
University Radiation Safety Committee must review occupational radiation
exposures. The Radiation
Safety Officer ensures that training is given, will review authorized
users’ procedures and physical layouts, and will investigate radiation
exposures that exceed ten percent of the annual limit.
The Authorized User will ensure that laboratory personnel are
properly trained and will consult with the RSO with regard to keeping
exposures ALARA. The
radiation worker will consider ALARA when conducting research in the
laboratory and will consult with the Authorized User or the Radiation
Safety Office when safety or other laboratory practices are in question. The
University of Pittsburgh has set an ALARA action level at 10 percent of
the annual Federal and State radiation exposure limits. Annual cumulative radiation exposures are reviewed each
calendar quarter. Action
levels are at 10%, 30% and 80% of the annual allowable dose. If it is
determined through monitoring or calculation that any worker has exceeded
30 percent of the applicable radiation exposure limits, an investigation
will be conducted to determine the cause of the exposure and to develop
methods to control future exposures.
A summary of exposure for any individuals exceeding these levels is
presented to the University Radiation Safety Committee at it’s next
quarterly meeting. B. EXTERNAL RADIATION PROTECTION
PRINCIPLES TIME Radiation
doses are directly proportional to the exposure time in the field.
If the time spent in a given radiation field is doubled, the
worker's dose is doubled. Therefore,
to limit radiation doses, the time spent in the field must be limited. Radiation
Dose DISTANCE The
radiation dose received from a source is inversely proportional to the
square of the distance of separation.
If the distance is increased ten-fold the exposure will be cut down
to one percent. Thus, the
distance of separation between a person and a "point" source has
a relatively greater influence on dose than the time factor. Radiation
dose SHIELDING Any
substance may serve to attenuate radiation to acceptable levels provided
sufficient thickness is used. Certain
materials, however, are more effective in shielding certain types of
radiation. Alpha particles
are stopped by an ordinary sheet of paper or a few inches of air. Beta particles although more penetrating than alpha, can be absorbed
readily and completely. Figure
4 shows the shielding required for complete absorption of beta rays of
various energies in various substances.
For example, beta rays of one million electron volts (MeV) are
completely absorbed by 0.15 cm of aluminum.
Gamma rays and x-rays of a single energy (monoenergetic) are attenuated exponentially; therefore, theoretically it is not possible to attenuate the radiation completely, although the exposure rate can be reduced by any desired factor. Thus, if a certain thickness of absorber, the half-value layer (HVL), reduces the dose to one-half the initial amount, then a thickness of three such layers will reduce the dose to one-eighth (˝ x ˝ x ˝) the initial amount. Similarly three tenth-value layers (TVL) will reduce the dose to 1/1000 of the initial amount (1/10 x 1/10 x 1/10). Shielding materials of high density and high atomic number, such as lead, are generally the most effective absorbers or shields for x- and gamma rays. Thus, less thickness and weight per square foot is required for such materials. However, steel, concrete, brick, or other materials can provide the same degree of protection if used in appropriately greater thicknesses. C. INTERNAL RADIATION PROTECTION PRINCIPLES An
internal radiation hazard exists when radionuclides can enter the body by
ingestion or inhalation, through wounds, or by direct absorption through
intact skin. The radiation
doses are often difficult to evaluate and depend on many factors such as
the physical and chemical form of the material, the mode of entry, and the
individual's metabolism. A
certain quantity of radioactive material within the body represents a
greater hazard than the same activity as an external source because the
tissue is irradiated continuously until the material has decayed or been
eliminated. Even weakly
penetrating radiations such as low-energy beta particles present a hazard
since all their energy will be dissipated in the tissue. The
principal means of protection from internal radiation is containment of
the radioactive source. Control
measures must be taken to prevent the contamination of working surfaces,
equipment, and personnel. The
following covers some of these safety precautions and procedures. D.
GENERAL PRECAUTIONS AND SAFETY
PROCEDURES WHEN WORKING WITH RADIOACTIVE MATERIALS
E.
EMERGENCY PROCEDURES In
case of a spill of radioactive material, the following procedures should
be performed:
In
case of personnel contamination, the following procedures should be
performed:
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Radiation Safety Office Webmaster Revised February 14, 2006 |
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