CRC handbook of laboratory Safety - Chapter 5 pptx

Furr, A. Keith Ph.D. "NONCHEMICAL LABORATORIES"
CRC Handbook of Laboratory Safety
Edited by A. Keith Furr, Ph.D.
Boca Raton: CRC Press LLC,2000
Chapter 5
NONCHEMICAL LABORATORIES
I. INTRODUCTION
The emphasis in the previous chapters has been on laboratories in which the primary
concerns were due to the use of chemicals, although in order to not completely avoid a topic
unnecessarily, some of the problems arising in other types of operations have been
addressed. For example, in the latter part of the last chapter some serious issues involving
problems with specific contagious diseases were discussed due to the increasing importance
these diseases have in our society and in our laboratories , as a continuation of the topic of
health effects. The problems of dealing with infectious waste were considered at some length
as well as chemical wastes as part of the larger problem of dealing with hazardous wastes. In
this chapter laboratory operations which involve special problems in other classes of
laboratories will be presented in greater detail. However, in responding to these special
problems, one should be careful not to neglect the safety measures associated with those
hazards already covered.
II. RADIOISOTOPE LABORATORIES
Exposure of individuals to ionizing radiation is a major concern in laboratories using
radiation as a research tool or in which radiation is a byproduct of the research. Although
there are many types of research facilities in which ionizing radiation is generated by the
equipment, e.g., accelerator laboratories, X-ray facilities, and laboratories using electron
microscopes, the most common research application in which ionizing radiation is a matter of
concern is the use of unstable forms of the common elements which emit radiation. A very
brief discussion of some atomic and nuclear terms will be given next, with apologies for those
not requiring this introduction to the subject.
A. Brief Summary of Atomic and Nuclear Concepts
An atom of an element can be simply described as consisting of a positively charged
nucleus and a cloud of negatively charged electrons around it. The electron cloud defines

the chemical properties of the atom, which have been the subject up until now, while the
processes primarily within the nucleus give rise to the nuclear concerns which will be
addressed next. Although the nucleus is very complex, for the present purposes an atom of a
given element may be considered to have a fixed number of positive protons in the nucleus,
equal in number to the number of electrons around the neutral atom, but can differ in the
number of neutral neutrons, the different forms being called isotopes. It is the property of the
unstable forms, or radioisotopes, to emit radiation which makes them useful, since their
chemical properties are essentially identical to the stable form of the element (where a stable
form exists; for elements with atomic numbers greater than that of bismuth, there are no
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completely stable forms). The radiation which the radioisotopes emit allows them to be
distinguished from the stable forms of the element in an experiment. There are three types of
radiation normally emitted by various radio isotopes, alpha (α) particles, electrons (β), and
gamma rays (γ). The properties of these radiations will be discussed later. A fourth type of
radiation, neutrons, may be emitted under special circumstances, by a small number of
radioactive materials. Most laboratories will not use materials emitting neutrons. The
properties of these radiations will be discussed in more detail later.
B. Radiation Concerns
The radiation which makes radioisotopes useful also makes their use a matter of concern
to the users and the general public. Exposure to high levels of radiation is known to cause
health problems; at very high levels, death can follow rapidly. At lower, but still substantial
levels, other health effects are known to occur, some of which, including cancer, can be
delayed for many years. At very low levels, knowledge of the potential health effects is much
more uncertain. The generally accepted practice currently is to extrapolate statistically known
effects on individuals exposed to higher levels to large groups of persons exposed to low
levels of radiation in a linear fashion. The concept is similar to the use of higher concen-
trations of chemicals using a limited number of animals in health studies of chemical effects,
instead of more normal concentrations in a very large number of test animals. There are some
who question the validity of this assumption in both cases, but it is a conservative
assumption and, in the absence of confirmed data, is a generally safe course of action to

follow. However, the practice may have led to a misleading impression of the risks of many
materials. When a scientist makes the statement that he does not know whether a given
material is harmful or not, he is often simply stating in a very honest way that the data do not
clearly show whether, at low levels of use or exposure, a harmful effect will result. It does not
necessarily imply, as many assume, that there is a lack of research in discovering possible
harmful effects. In many cases, major efforts have been made to unambiguously resolve the
issue, as in the case of radiation, and the data do not support a definite answer. There are
levels of radiation below which no harmful effects can be detected directly. In the case of
radiation, there is even a substantial body of experimental data (to which proponents of a
concept called “hormesis” call attention) that supports possibly positive effects of radiation
at very low levels. This position is, of course, very controversial. However, in chemical areas
there are many examples of chemicals essential to health in our diets in trace amounts that are
poisonous at higher levels. It is not the intent of this section to attempt to resolve the issue of
the effects of low-level radiation, but to emphasize that there are concerns by many
employees and the general public. It may well be that, by being very careful not to go beyond
known information, scientists have actually contributed to these concerns. Another way of
looking at the issue, and certainly a more comforting way, is that many unsuccessful attempts
have been made to demonstrate negative effects at low levels. Radiation levels which
normally accompany the use of radioisotopes are deliberately kept low, and the perception of
risk by untrained individuals may be overstated. However, a linear dose-effect relation is the
accepted basis for regulatory requirements at this time, and until better data are available
scientists using radioactive substances must conform to the standards. Users owe it to
themselves and the public to use the materials in ways known to be safe. However, as a
general concept, it would be wise for scientists, when speaking to persons not trained in their
field, to be sure that when they say they do not know of possible harmful effects of any
material, that this statement is understood to be an informed uncertainty where this is the
case, as opposed to being based on a lack of effort.
It is unfortunate that there is so much concern about radiation since there are many
beneficial effects, but because of the dramatization of the concerns, many individuals fear
radiation out of all proportion to any known risks. In an opinion poll in which members of the

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general public were asked to rank the relative risks of each of a number of hazards, nuclear
radiation was ranked highest but in reality, was the least dangerous of all the other risks
based on known data with all the others being much more likely to cause death or injury than
radiation. Individuals who urgently have needed X-rays, the application of diagnostic use of
radioactive materials, or radiation therapy have declined to have them because of this
heightened fear. Used properly, radiation is an extremely valuable research tool and has many
beneficial aspects. Used improperly, it can be dangerous, but so can many other things in the
laboratory, many very much more so.
C. Natural Radioactivity
A common misconception is that radiation is an artificial phenomenon. Many of the most
commonly used radioisoto pes have been created artificially, but there are abundant sources
of natural radiation which emit radiation of exactly the same three types as do artificially
created radioisotopes. Elements such as potassium and carbon, which are major constituents
of our body have radioactive isotopes. Many other elements, such as the rare earths, have
radioactive versions. Every isotope of elements with atomic numbers (i.e., the number of
protons in the nucleus of the element, or the number of electrons around the nucleus in a
neutral atom) above 83 is unstable and these elements are common in the soils and rocks
which make up the outer crust of the earth. There are areas in the world in which the natural
levels of radiation could significantly exceed that permitted for the general public resulting
from the operation of any licensed facility using radioisotopes. Radiation constantly
bombards us from space due to cosmic rays. Persons who frequently take long airplane
flights receive a significantly increased amount of radiation over a period of time compared to
persons who fly rarely or not at all. Arguments that these natural forms of radiation are
acceptable because they are natural has absolutely no basis in fact. As was mentioned earlier,
there are only a modest number of varieties of radiation, and these are produced by both
natural and artificially produced radioactive materials. Similarly, there are only a few ways in
which radiation may interact with matter, and they also are the same for all sources of
radiation.

The acknowledgment of natural sources of radiation is not intended to minimize concerns
about radiation, even the natural forms, but to point out that if there are concerns about low
levels of radiation, then these natural levels must be considered as well as the artificial
sources. One of the naturally occurring radioactive materials, radon, has been receiving much
attention and may be a significant hazard, perhaps contributing to an increase of 1 to 5% of
the number of lung cancer deaths each year. This estimate, as in most cases dealing with
attribution of specific effects of low levels of radiation, is supported by some and disputed by
others. Note, however, that even in this case at least 95 to 99% of the lung cancer deaths are
attributable to other causes. Radon as an issue will be discussed in a separate section later in
this chapter. An isotope of potassium, an essential element nutritionally and present in
substantial amounts in citrus fruits and bananas, for example, emits significant amounts of
very penetrating radiation.
There are various estimates of the average source of radiation exposure for most indi-
viduals. An article by Komarov,
1
who is associated with the World Health Organization,
provides the following data about sources of radiation: 37% from cosmic rays and the
terrestrial environment, 28% from building materials in the home, 16% from food and water,
12% from medical usage (primarily X-rays), perhaps 4% from daily color television viewing,
2% from long-distance airplane flights, and 0.6% (under normal operating conditions) from
living near a nuclear power plant. Note that the medical exposure to radiation is 20 times
larger than from nuclear power plants even for those living near one. The Komarov article was
written before the Chernobyl incident, but even this outstanding example of poor
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management is not sufficient to change the general picture. Unlike the Chernobyl reactor,
commercial nuclear power plants in the United States are protected by very strong
confinement enclosures to prevent unscheduled releases. In the case of the Three-Mile Island
incident, in which the reactor core melted down, the confinement enclosure performed as
designed and minimal amounts of radioactive material were released. As the news media
reported some time after the initial furor, “the biggest danger from Three-Mile Island was

psychological fear,” to which the media contributed significantly by exaggerated news
reports of the potential dangers.
In summary, radiation is a valuable research tool. In order to prevent raising public
concerns and perhaps lead to further restrictions on its use, scientists need to be scrupulous-
ly careful to conform to accepted standards governing releases or over exposures. Fortu-
nately, for common uses of radiation in research laboratories, this goal is easily achieved with
reasonable care.
D. Basic Concepts
Each scientific discipline has its own special terms and basic concepts on which it is
founded. This section is, of course, not necessary for most scientists who routinely work with
radiation, but it may be useful for establishing a framework within which to define some
needed terms. As scientists work with accelerators of higher and higher energies, the concept
of matter is at once growing more complex and simpler; more complex in that more entities are
known to make up matter, but simpler in that theorists working with the data generated by
these gigantic machines are developing a coherent concept unifying all of the information.
For the purposes of this discussion, a relatively simple picture of the atom will suffice, as
noted earlier.
1. The Atom and Types of Decay
In the simple model of the atom employed here, as briefly described earlier in this chapter,
the atom can be thought of as consisting of a very small dense nucleus, containing positively
charged particles called protons and neutral particles called neutrons, surrounded by a cloud
of negatively charged electrons. The number of protons and the number of electrons are equal
for a neutral atom, but the number of neutrons can vary substantially, resulting in different
forms of an element called, as already noted, isotopes of the element. Some elements have
only one stable isotope, although tin has ten. There are unstable isotopes, logically called
radioisotopes, in which, over a statistically consistent time, a transition of some type occurs
within the nucleus. Different types of transitions lead to different types of emitted radiation.
Hydrogen, for example, has two stable forms and one unstable one, in which a transition
occurs to allow an electron to be generated and emitted from the nucleus, producing a stable
isotope of helium. Prior to the transition, the electron did not exist independently in the

nucleus. A neutron is converted to a proton in the process, and the electron is created by a
transformation of energy into matter. This process is called beta decay. No element with more
than 83 protons in the nucleus has a completely stable nucleus, although some undergo
transitions (including by processes other than beta decay) extremely slowly.
In some cases, the mass energy of the nucleus favors emission of a positive electron
(positron) instead of a normal electron which has a negative charge. This is called positive
beta decay or positron decay. Here a proton is converted into a neutron. A competitive
process to positive beta decay is electron capture (
ε) in which an electron from the electron
cloud around the nucleus is captured by the nucleus, a proton being converted into an
neutron in the process. In the latter process, X-rays are emitted as the electrons rearrange
themselves to fill the vacancy in the electron cloud. However, following positron emission,
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the positive
Table 5.1 Properties of Radioactive Emissions
Type Mass (amu) Charge (Electron Units) Range of Energy
Alpha (a) 4 +2 4-6 MeV
Beta (B) 1/1 840 +1 eVs-4 MeV
Gamma 0 0 eVs-4 MeV
X-Rays 0 0 eVs-100 KeV
An amu is the mass of a single nucleon based on the 1/12th the mass of a carbon-12 nucleus.
electron eventually interacts with a normal electron in the surrounding medium, and the two
vanish or annihilate each other in a flash of energy. The amount of energy is equal to the
energy of conversion of the two electron masses according to E = mc
2
. This amounts to, in
electron volts, 1.02 million electron volts, or 1.02 MeV. In order to conserve momentum, two
photons or gamma rays of 0.511 MeV each are emitted 180
"

apart in the process.
In many case, the internal transitions accompanying adjustments in the nucleus results in
the emission of electromagnetic energy, or gamma rays. These can be in the original or parent
nucleus, in which case they are called internal transitions, and the semi-stable states leading
to these transitions are called metastable state s. More often, the gamma-emitting transitions
occur in the daughter nucleus after another type of decay such as beta decay (metastable
states can exist in the daughter nucleus also). The gamma emission distribution can be very
complex. In some instances, the internal transition energy is directly transferred to one of the
electrons close to the nucleus in a process called internal conversion, and the electron is
emitted from the atom. In this last case, energy from transitions in the orbital electron cloud is
also emitted as X-rays.
Finally, the most massive entity normally emitted as radiation is the alpha (a) particle
which consists of a bare (no electrons), small nucleus having two protons and two neutrons.
The nucleons making up an alpha particle are very strongly bound together, and unlike
electrons, the alpha particle appears to exist in the parent nucleus as a cohesive unit prior to
the decay in our simple model. This process is somewhat more rare than
β or γ decay.
The processes briefly described above are the key decay processes in terms of safety in
the use of radioisotopes. There is another very important aspect of the decay processes, and
that is the energy of the emitted radiation. The electrons emitted in beta decay can have
energies ranging from a few eV to between 3 and 4 MeV. There is an unusual feature of the
beta decay process in that the betas are not emitted monoenergetically from the nucleus as
might be expected, and as does occur for alpha and gamma decay. The most probable energy
of the betas in a decay process is approximately one third of the maximum energy beta emitted
in the process. The reason is that, in addition to a beta being emitted, another particle, called a
neutrino, of either zero mass or very close to it, is emitted simultaneously and shares the
transitional energy, with varying amounts going to the two entities. The neutrino does not
play a role in radiation safety as it interacts virtually negligible with matter, although its
existence is very important for many other reasons. Gammas can have a similar range of
energies to that of electrons, but the energies of the gammas are discrete instead of a

distribution.
Alpha particles have a relatively high energy, normally ranging from 4 to 6 MeV. The
decay of alphas with lower energies is so slow that it occurs very rarely while with an energy
just a little higher, the nucleus decays very rapidly. The high energy, accompanying the high
mass and the double positive charge, make the alpha particle a particularly dangerous type of
radiation, if it is emitted in the proximity of tissue which can be injured. This last is an
important safety qualification as will be seen later. Table 5.1 summarizes the properties of the
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Figure 5.1 Schematic representation of the decay process.
types of radiation.
Graphically the decay process can be depicted as shown in Figure 5.1, where N = the
neutron number and Z = the nuclear charge. The box with N,Z is the parent nucleus and the
others are the possible daughters for the processes shown.
2. The Fission Process
A major omission deliberately not mentioned in the preceding Section is not involved in
most laboratories using radioisotopes. However, without this process many of the commonly
used radioisotopes would not be available, since they are obtained from reprocessing spent
fuel and recovery of the remnants left over after the fission process. The process of fission
describes the process by which a few very heavy atoms decay by splitting into two major
components and a few neutrons, accompanied by the release of large amounts of energy,
~200 MeV. The process can be spontaneous for some very heavy elements, e.g., Californium-
252 but also can be initiated by exposing specific heavy nuclei to neutrons. There are no
common radioisotopes that normally emit neutrons, but there are several interactions in which
a neutron is generated. Among these are several reactions in which a gamma ray interacts
with beryllium to yield neutrons, so that a portable source of neutrons can be created. There
are many other ways to generate neutrons but there is no need to describe these in this book.
However, if a source of neutrons, n, is available and is used to bombard an isotope of
uranium,
235
U, the following reaction can occur.

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n +
235
U -> X+Y + ~2.5n + energy (1)
Here, X and Y are two major atomic fragments or isotopes resulting from the fission
process. On average about 2.5 neutrons are emitted in the reaction plus energy. The process
is enhanced if the initiating neutrons are slowed down until they are in or near thermal
equilibrium with their surroundings. X and Y themselves will typically decay after the original
fission event, a few by emitting additional neutrons, as well as betas and gammas. As noted
earlier, about 200 MeV of energy are released in the process, much of it as kinetic energy
shared by the particles. Some of these fission fragments are long lived, and can be chemically
separated to provide radioisotopes of use in the laboratory. These fission fragment derived
radioisotope s are the major source of the byproduct radioisotopes regulated by the Nuclear
Regulatory Commission (NRC). The fission reaction can, under appropriate circumstances, be
self-sustaining in a chain reaction . In some configurations, the chain reaction is extremely
rapid, and an atomic bomb is the result. However, by using the neutrons emitted by the
fission fragments (called delayed neutrons), the process can be controlled safely in a reactor.
Over a period of time, the fission products build up in the uranium fuel eventually can be
recovered when the fuel element is reprocessed.
Additional radioactive materials or radioisotopes are made by the following reaction:
n +
A
X->
(A+1)
y* + a (2)
The asterisk indicates that the product nucleus, Y may be unstable and will undergo one
(or more) of the modes of decay discussed previously. The 'a’ indicates that there may be a
particle directly resulting from the reaction. In many cases, the source of neutrons for
radioisotopes created by this reaction is a nuclear reactor so these radioactive materials also

are “byproduct materials, ” and are regulated by the Nuclear Regulatory Commission or State
surrogates.
Plutonium is made in nuclear reactors by the above reaction where
238
U is the target
nucleus. Although there are other reactions using different combinations of particles in
Equation 2, in most cases these require energetic bombarding particles generated in accelera-
tors. Also, since there are no common radioisotopes that generate neutrons, there is
essentially no probability that other materials in laboratories will be made radioactive by
exposure to radiation from byproduct materials.
Materials which will undergo fission and can be used to sustain a chain reaction are, in
the nomenclature of the NRC, “special” nuclear materials. These include the isotopes of
uranium with mass numbers 233 and 235, materials enriched in these isotopes, or the
artificially made element, plutonium. Materials which have uranium or thorium, which also has
a fissionable isotope, in them to the extent of 0.05% are called source materials.
3. Radioactive Decay
An important relationship concerning the actual decay of a given nucleus is that it is
purely statistical, dependent only upon the decay constant for a given material, i.e., the
activity A, is directly proportional to the number, N, of unstable atoms present:
Activity = A = dN/dt = C N (3)
This can be reformulated to give the number of radioactive atoms N at a time t in terms of
the number originally present.
N(t) = N
0
e
8t
(4)
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~
where

λ = ln2/τ.
Table 5.2 Typical Decay of a Group of 1000 Radioactive Atoms
Number Time (t) Number Time (t)
1000 0 14 6
502 1 7 7
249 2 4 8
125 3 1 9
63 4 1 10
31 5 0 11
Equation 4 shows that during any interval, t = τ, theoretically half of the unstable nuclei at
the beginning of the interval will decay. In practice, approximately half will decay in a half-
life, τ. This is illustrated in Table 5.2.
The data in this table illustrate clearly that when small numbers are involved, the statistical
variations cause the decrease to fluctuate around a decay of about one half of the remaining
atoms during each successive half-life, but obviously between 3 and 4 half-lives in this table,
it would have been impossible to go down by precisely half. The table also illustrates a
fairly often used rule-of-thumb: after radioactive waste has been allowed to decay by 10 half-
lives, the activity has often decayed sufficiently to allow safe disposal. This, of course,
depends upon the initial activity.
The daughter nucleus formed after a decay can also decay as can the second daughter,
and so forth. However, eventually a nucleus will be reached which will be stable. This is, in
fact, what occurs starting with the most massive natural elements, uranium and thorium. All of
their isotopes are unstable, and each of their daughters decays until eventually stable iso-
topes of lead are reached. The existence of all of the elements above atomic number 83 owe
their existence to the most massive members of these chains that have very long half-lives
that are comparable to the age of the earth, so a significant fraction remains of that initially
present.
4. Units of Activity
The units of activity are dimensionally the number of decays or nuclear disintegrations
per unit time. Until fairly recently, the standard unit to measure practical amounts of activity

was the curie (Ci), which was defined to be 3.7 x 10
10
disintegrations per second (dps). Other
units derived from this were the millicurie (mCi) or 3.7 x 10
7
dps, the microcurie (µ Ci) or 3.7 x
10
4
dps, the nanocurie (nCi) or 37 dps and the picocurie (pCi) or 0.037 dps. Many health
physicists prefer to use disintegrations per minute (dpm), and the NRC also prefers the data
logged in laboratory surveys to be expressed in dpm. The curie was originally supposed to
equal the amount of activity of 1 g of radium. This unit, and the derivative units, are still the
ones most widely used daily in this country; however, an international system of units, or SI
system, has been established (and is used in scientific articles). In this system, one
disintegration per second is defined as a becquerel (Bq). Larger units, which are multiples of
10
3
, 10
6
, 10
9
, and 10
12
, are indicated by the prefixes kilo, mega, giga, and tera, respectively. In
most laboratories that use radioisotopes as tracers, the quantities used are typically about 10
4
to 10
8
dps. There are other uses of radioisotopes (e.g., therapeutic use of radiation) which use
much larger amounts.

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5. Interaction of Radiation with Matter
a. Alphas
As an alpha particle passes through matter, its electric field interacts primarily with the
electrons surrounding the atoms. Because it is a massive particle, it moves comparatively
slowly and spends a relatively significant amount of time passing each atom. Therefore, the
alpha particle has a good opportunity to transfer energy to the electrons by either removing
them from the atom (ionizing them) or raising them or exciting them to higher energy states.
Because it is so much more massive than the electrons around the atoms, it moves in short,
straight tracks through matter and causes a substantial amount of ionization per unit distance.
An alpha particle is said to have a high linear energy transfer (LET). A typical alpha particle
has a range of only about 0.04 mm in tissue or about 3 cm in air. The thickness of the skin is
about 0.07 mm so that a typical alpha particle will not penetrate the skin. However, if a material
that emits alphas is ingested, inhaled, or, in an accident, becomes imbedded in an open skin
wound, so that it lodges in a sensitive area or organ, the alpha radiation can cause severe
local damage. Since many heavier radioactive materials emit alpha radiation, this often makes
them more dangerous than materials that emit other types of radiation, especially if they are
chemically likely to simulate an element retained by the body in a sensitive organ. If they are
not near a sensitive area, they may cause local damage to nearby tissue, but this may not
cause appreciable damage to the organism as a whole.
b. Betas
Beta particles are energetic electrons. They have a single negative or positive charge and
are the same mass as the electrons around the atoms in the material through which they are
moving. Normally, they also are considerably less energetic than an alpha particle. They
typically may move about two orders of magnitude more rapidly than alpha particles. They
still interact with matter by ionization and excitation of the electrons in matter, but the rate of
interaction per unit distance traveled in matter is much less. Typically, beta radiation, on the
order of 1 MeV, can penetrate perhaps 0.5 cm deep into tissue, or about 4 meters of air,
although this is strongly dependent upon the energy of the beta. Low-energy betas, such as

from
14
C, would penetrate only about 0.02 cm in tissue or about 16 cm in air. Therefore, only
those organs lying close to the surface of the body can be injured by external beta irradiation
and then only by the more energetic beta emitters. Radioactive materials emitting betas taken
into the body can affect tissues further away than those that emit alphas, but the LET is much
less.
There is a secondary source of radiation from beta emitters. As the electrons pass through
matter, they cause electromagnetic radiation called “bremstrahlung,” or braking radiation to be
emitted as their paths are deflected by passing through matter. The energy that appears as
bremstrahlung is approximately ZE/3000 (where Z is the atomic charge number of the
absorbing medium and E is the
β energy in MeV.) This is not a problem with alpha particles
since their paths through matter are essentially straight. Bremstrahlung radiation can have
important implications for certain energetic beta emitters such as
32
P. Protective shielding for
energetic beta emitters should be made of plastic or other low-Z material instead of a high-Z
material such as lead. Because of the silicon in glass, even keeping
32
P in a glass container
can substantially increase the radiation dose to the hands while handling the material in the
container as compared to the exposure that would result were bremstrahlung not a factor.
c. Gammas
Since gamma rays are electromagnetic waves, they are not charged and do not have any
mass, they interact differently with matter than do alpha and beta particles, although the net
effect is usually still ionization of an orbital electron. They interact with the electrons in matter
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Figure 5.2 Photoelectric absorption coefficient for lead.
by three different mechanisms. In order to provide an understanding of the safety

implications, a brief elaboration of these mechanisms follows. Until one of the three processes
takes place, the gamma ray can continue to penetrate matter without hindrance.
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Figure 5.3 Scattering coefficient for lead as a function of
energy.
i. Photoelectric Effect
The gamma ray interacts with electrons around an atom. Electrons with which they interact
normally are completely removed from the atom, i.e., the atom is ionized. In a photoelectric
effect process, all the energy of the gamma ray is transferred to the electron and the gamma
ray no longer exists. The photoelectric effect mechanism is dependent upon the gamma
energy as shown in Figure 5.2. For low energy photons, the photoelectric effect depends
upon the atomic number of the absorber, approximately as Z
4
. As energies increase, the
importance of the atomic number of the absorber decreases. The scattered electron interacts
as would a beta.
ii. Compton Effect
The gamma ray can also scatter from an electron, transferring part of its energy to the
electron and thus becoming scattered as a lower energy gamma. There is an upper limit to the
amount of energy that can be transferred to the electron by this mechanism, so that in every
scattering event, a gamma ray remains after the interaction. Dependent upon the energy
transferred, the residual gamma can be scattered in any direction, relative to the original
direction, up to 180
"
. This has important implications on shielding, since gammas can be
scattered by the shielding itself, or by other nearby materials into areas shielded by a direct
beam. Equation 5 gives the energy of the scattered gamma as a function of the angle of
scattering. The interaction with matter is considerably less dependent upon the energy of the
gamma. This is shown in Figure 5.3. Compton scattering is the primary mechanism of

interaction for low atomic number elements, and decreases in relative importance as the atomic
number increases.
(5)
( )
E
E
E m C
e
=
+ -1 1
2
/ ( cos )
q
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iii. Pai r Production
If the energy of the gamma is greater than the energy needed to create an electron-
positron pair, 1.02 MeV, then the gamma can interact with the absorbing medium to create the
pair of electrons, an electron and a positron. The probability of this process increases as the
energy increases. The excess energy over 1.02 MeV is shared by the two particles. The
increases with the atomic number of the absorber, approximately proportionally to Z
2
+ Z.
Gamma rays can penetrate deeply into matter, in theory infinitely, since unless the gamma
interacts with an atom, it will go on unimpeded, just as in theory a rifle bullet fired into a forest
can continue indefinitely unless it hits a tree (assuming no loss of energy for the bullet due to
air friction). The intensity I of the original radiation at a depth x in an absorbing medium
compared to the intensity of the radiation at the surface I is:
I = I
0
e

-:x
(6)
This equation is literally true if only gammas of the original energy are considered. If
Compton scattering and the pair-production process are included, the decrease in the total
number of gammas is less than that given by Equation 6, because of the scattered gammas
from the Compton process, and the contribution of the annihilation gammas as the positron
eventually is destroyed by interacting with a normal electron. The actual increase in the
radiation levels is dependent on the gamma energy and the geometry of the scattering
material.
If the total effect of all three mechanisms is considered at low and high energies, higher Z
©2000 CRC Press LLC
o

Figure 5.4 Pair-production coefficient for lead as a function of
energy.
absorbers interact with gammas more strongly. However, between about 1 and 3 MeV
is a relatively minor difference in the total absorption coefficient as a function of atomic
number as shown in Figure 5.5. The discontinuities at lower energies are due to enhanced
probability of interactions with electrons at the ionization thresholds.
As can be noted, all of the mechanisms by which a gamma interacts with matter (except
the very small number of instances in which the gamma ray interacts with a nucleus) result in
the energy being transferred to an electron, so a gamma is considered to have the same low
LET characteristics as do betas. At very low energies the linear energy transfer characteristics
of electrons increase some. However, unless a beta emitter is taken into the body, most
internal organs will not be affected by beta radiation, while gammas can penetrate deeply into
the body and injure very sensitive organs such as the blood-forming tissues. Thus, of the
three types of radiation, gamma rays are usually considered the most dangerous for external
exposures.
iv. Neutrons
As mentioned earlier, neutron radiation is rarely encountered in most laboratories that use

radioisotopes in research programs. However, it is useful to understand the difference in the
mechanisms by which a neutron interacts with matter compared to those involving other
types of radiation since neutron radiation may make the matter with which it interacts
radioactive. The neutron has no charge, but it does have about one fourth of the mass of an
alpha particle, so that it does have an appreciable mass compared to the atoms with which it
interacts.
An equation similar to Equation 6 gives the number of neutrons N, with an initial energy
E, of an original number N
0
penetrating to a depth x in matter. Note that in both Equations 6
and 7, the units of x are usually converted into mg/cm
2
for the commonly tabulated values of
©2000 CRC Press LLC
Figure 5.5 Total mass attenuation coefficient for ( absorption in lead as a
function of energy.
µ and σ.
N = N
0
e
-σ
(7)
A neutron does not, as do electrons, alpha particles, and gammas, interact with the orbital
electrons, but instead interacts directly with the nucleus. The neutron is not repelled by the
positive charge on the nucleus as is the alpha because it has no charge. It is either scattered
(elastically or inelastically) or captured by the nucleus. In a typical capture process usually
several “capture” gammas with a total energy of about 8 MeV are emitted (the energies are
somewhat less for some lighter nuclei). Thus, by this mechanism alone, the neutron could be
considered more harmful than other radiations. Further, the nucleus in which it is captured
may have been made radioactive, and the charge on the nucleus could change, so that the

atom would no longer be chemically equivalent to its original form. In any event, the energy
transferred to the participants in the interaction normally would be more than sufficient to
break the chemical bonds.
Scattering events also typically would transfer enough energy to break the chemical
bonds as long as the initial energy of the neutron is sufficiently high. As with Compton
scattered gammas, the scattered neutrons can be scattered into virtually any direction, so that
the equivalent of Equation 7 for neutrons of all energies would, as for gammas, have to be
modified to include a buildup factor.
No figure showing the systematics of the reaction mechanisms will be given here because
the relationships are extremely complex, varying widely not only between elements, but
between isotopes of the same element. In addition, the interaction probabilities can vary
extremely rapidly as a function of energy, becoming very high at certain “resonant” energies
and far less only a few electron volts above or below the resonances. However, a few
©2000 CRC Press LLC
x

generalizations are possible. The probability of the capture process, excluding resonance
effects, typically increases as the energy of the neutrons become lower, and for specific
isotopes of certain elements, such as cadmium, gadolinium, samarium, and xenon, is extremely
high at energies equivalent to thermal equilibrium (about 0.025 eV for room temperature
matter). Energy can be lost rapidly by neutrons in scattering with low-Z materials, such as
hydrogen, deuterium (
2
H), helium, and carbon. Interposing a layer of water, paraffin, or
graphite only a few inches thick, backed up by a thin layer (about 1/32 inch) of cadmium, in a
beam of fast neutrons makes an effective shield for a beam of neutrons. Paraffin wax, in which
boric acid has been mixed also makes an effective and cheap neutron
shield (
10
B has quite a respectable capture cross-section at thermal neutron energies).

Overall, the estimate of the danger of neutrons interacting with matter is estimated to be
about ten times that of a gamma or electron, although this varies depending upon the energy
of the neutrons, thermal neutrons are about two times as effective in causing atoms in tissue
to be ionized, for example, as are betas and gammas while neutrons of 1 to 2 MeV energy are
about 11 times more damaging.
6. Units of Exposure and Dose
There are two important concepts in measuring the relative impact of radiation on matter:
one is the intensity of the radiation field, which represents a potential exposure problem, and
the other is the actual energy deposited in matter, or the dose. Further, as far as human safety
is concerned, the amount of energy absorbed in human tissue is more important than that
absorbed in other types of matter. Each of these quantities have been assigned specific units
in which they are measured.
The original unit of measuring radiation intensity was the roentgen, defined as the amount
of X-ray radiation that would cause an ionization of 2.58 x 10
-4
coulombs per kilogram of dry
air at standard temperature and pressure. As noted, the dose or energy deposited in matter is
more important, so another unit was subsequently defined, the rad, which was defined as the
deposition of 0.01 joules per kilogram of matter. An exposure to 1 roentgen would result in an
absorbed dose of 0.87 rads in air. A third unit, the rem, was subsequently defined which
measured the equivalent dose, allowing for the relative effectiveness of the various types of
radiation in causing biological damage. This originally was allowed for by multiplying the
absorbed dose in rads by a relative biological effectiveness factor (RBE), to obtain a dose
equivalent for tissue for the different varieties of radiation. Later, it was decided to restrict the
term RBE to research applications and an equivalent multiplier called the quality factor, Q, was
substituted. For practical purposes, RBE and Q factors are equivalent, although the latter is
the one now commonly used.
The terms rads and rems are still used by most American health physicists in their daily
work, and the current NRC regulations use these terms, as they do the curie and its derivative
units. However, there are internationally accepted SI units for dose and also for activity. The

equivalent units are:
1 Gray (Gy) = 1 joule/kilogram = 100 rad = absorbed dose
1 Sievert (Sv) = 1 Gray x Q x N = dose equivalent (N is a possible modifying factor,
assigned a value of 1 at this time)
1 Sievert = 100 rem = dose equivalent
The quality factors for the various types of radiation are listed in Table 5.3. For neutrons
of specific energies, the quality factor can be found in 10 CFR 20, Table 1004.
This concludes this very brief discussion of some basic terms and concepts in radiation
physics that will be employed in the next few sections. Many important points and significant
features have been omitted that would be of importance primarily to professional health
©2000 CRC Press LLC
Table 5.3 Quality Factors
Type of Radiation
Betas, gammas, X-rays 1
Alphas 20
Thermal neutrons 2
Fast neutrons (~ I MeV) 20
Neutrons (unspecified energy) 10
physicists, but are of less importance to those individuals that use radiation as a research tool
to serve their more direct interests. The role of the Nuclear Regulatory Commission will be
heavily stressed because the NRC very strictly regulates all aspects of radiation involving
special nuclear materials and byproduct materials for safety and security through its licensing
and oversight functions.
E. Licensing
This section will be restricted to a discussion of licensing of radioisotopes or byproduct
materials, rather than other types of applications such as a research reactor. It has been some
time since any new applications for construction of a nuclear power plant in the United States
has been approved, and the number of operating non-governmental research reactors has
been diminishing. Several of these research facilities are either in the process of terminating
their license or going into an inactive status. At least some research reactors have closed

rather than renew their license, as they must do periodically, because of excessive costs
needed to meet the concerns of the public. The other major type of facility involved with
radiation, laboratories using X-ray units, are usually regulated by state agencies, although the
federal Food and Drug Administration sets standards for the construction of the machines
and their applications. X-ray facilities will be discussed in a separate section.
Radioactive materials fall into two classes as far as regulation is concerned. Radioactive
materials “yielded in or made radioactive by exposure to the radiation incident to the process
of producing or utilizing special nuclear material” are regulated by the NRC, or by equivalent
regulations in states with whom the NRC has entered into an agreement allowing for the
states to act as the regulatory agency within their borders. Radioactive materials that are
naturally radioactive or produced by means such as a cyclotron are regulated by the states in
most cases.
The licensing of byproduct material is regulated under 10 CFR Part 30 or 33. Licenses are
issued to “persons,” a term which may refer to an individual but may also mean organizations,
groups of persons, associations, etc. It is possible for individuals within an organization to
have separate licenses, although it is more likely that instead of several individuals having
separate licenses, an institution will apply for and be granted a license covering the entire
organization, if they can show that they have established an appropriate internal organization
so that they can ensure the NRC that the individual users will conform to the terms of the
license and regulations governing the use of radioactive materials. This second class of
licenses is denoted as a byproduct license of broad scope. There are different
types of broad licenses, A, B, and C. A type A license is the least restriction and allows users
to use radioisotopes as allowed in 10 CFR 30.100 Schedule A. A type B license is for users of
larger quantities of various radioisotopes, on the order of curies or more, and a type C license
©2000 CRC Press LLC

is for users of smaller quantities. Schedule A in 10 CFR, Part 33.100 defines the quantities
applicable to each of the last two licenses.
For most types of licenses of interest to research laboratories, the NRC has delegated
licensing authority to five regional offices in Pennsylvania, Georgia, Illinois, Texas, and

California. The current addresses of these regional offices can be obtained by writing to:
Director
Office of Nuclear Material Safety and Safeguards
U.S. Nuclear Regulatory Commission
Washington, D.C. 20555
Not all uses of radioisotopes require securing a license. There are many commercial
products, such as watch dials and other self-luminous applications, and some types of smoke
detectors that contain very small quantities of radioactive materials which the owner
obviously does not require a license to possess. However, those who take advantage of
exemptions must use no more than the “exempt quantities” listed in Schedule B, 10 CFR
Section 30.71. In Table 5.4,
the units are in microcuries. To convert to becquerels, multiply
the number given in microcuries by 37,000.
Any byproduct material that is not listed in Table 5.4, other than aipha-emitting byproduct
material, has an exempt quantity of 0.1
:Ci or 3700 Bq.
Most users of radioisotopes would find it necessary to use more than the exempt
quantities in Table 5.4 and should apply for a license. This is done through NRC Form 113,
which can be obtained from the NRC office in the local region. If the activity planned has the
potential for affecting the quality of the environment, the NRC will weigh the benefits against
the potential environmental effects in deciding whether to issue the license. For most
research-related uses of radioisotopes, environmental considerations will not usually apply,
although where the isotopes will be used in the field, outside of a typical laboratory, the
conditions and restrictions on their use to ensure that there will be no meaningful release into
the environment will need to be fully included in the application.
There are three basic conditions that the NRC expects the applicant to meet in their ap-
plication. In this context, “applicant” is used in the same sense as the word “person,” which
can be an individual or an organization, as noted earlier.
1. The purpose of the application is for a use authorized by the Act. Legitimate basic and
applied research programs in the physical and life sciences, medicine, and engineering

are acceptable programs.
2. The applicant
*s proposed equipment and facilities are satisfactory in terms of protect-
ing the health of the employees and the general public, and being able to minimize the
risk of danger to persons and property. The laboratories in which the radioisotopes are
to be used need to be in good repair and contain equipment suitable for use with
radioisotopes. Depending upon the level of radioactivity to be us ed and the scale of
the work program, this may mandate the availability of hoods designed for radio-
isotope use. It could require specific areas designated and restricted for isotope use
only, or the level of use and the amounts of activity may make it feasible to perform the
research on an open bench in a laboratory. In any event, it must be shown in the
application that the level of facilities and equipment must be adequate for the
proposed uses of radiation.
3. The applicant must be suitably trained and experienced so as to be qualified to use the
material for the purpose requested in a way that will protect the health of individuals
a nd minimize danger to life and property The experience and training must be
©2000 CRC Press LLC
documented in the application.
Following are the specific NRC requirements for approval of a Type A, Broad License.
The requirements for Type B and C licenses are a bit less stringent. Most major users will find
that complying with the terms of Type A licenses to be most appropriate.
“An application for a Type A specific license of broad scope will be approved if:
(b) The applicant satisfies the general requirements specified in Sec. 30.33;
(b) The applicant has engaged in a reasonable number of activities involving the use of
byproduct material; and
(c) The applicant has established administrative controls and provisions relating to
organization and management, procedures, record keeping, material control, and
accounting and management review that are necessary to assure safe operations,
including:
(1) The establishment of a radiation safety committee composed of such persons as a

radiological safety officer, a representative of management, and persons trained
and experienced in the safe use of radioactive materials;
(2) The appointment of a radiological safety officer who is qualified by training and
experience in radiation protection, and who is available for advice and assistance
on radiological safety matters; and
(3) The establishment of appropriate administrative procedures to assure:
(i) Control of procurement and use of byproduct material;
(ii) Completion of safety evaluations of proposed uses of byproduct material
which take into consideration such matters as the adequac y of facilities and
equipment, training and experience of the user, and the operating or handling
procedures; and
(iii) Review, approval, and recording by the radiation safety committee of safety
evaluations of proposed uses prepared in accordance with paragraph (c)(3)
(ii) of this section prior to use of the byproduct material.”
Under item(3)(iii) the Radiation safety Committee also approves individual users if
radioisotopes under the Broad License. In effect, they act as a local NRC governing use of
the radioisotopes.
Before granting the license, the NRC may require additional information, or may require
the application to be amended. The license is issued to a specific licensee and cannot be
transferred without specific written approval of the NRC. The radioisotopes identified in the
license can be used only for the purposes authorized under the license, at the locations
specified in the license. If the licensee wishes to change the isotopes permitted to be used, to
significantly modify the program in which they are used, or to change the locations where
they are to be used, the license must be amended. This typically takes a substantial length of
time, 1 to 3 months or even more not being unusual. Consequently, most substantial users of
radioisotopes usually do apply for a “broad” license under 10 CFR Part 33.
Under the terms of a broad license, the application usually covers a request to use ra-
dioisotopes with atomic numbers from 3 to 83, with individual limits on the quantities held of
specific isotopes, and an overall limit of the total quantity of all isotopes held at once. In
addition, there should be specific identification of sealed sources held separately by the

applicant on the license.
The license will be granted for a specific period, and the ending date will be written into
the license. If the licensee wishes to renew the license as the end of the license period
approaches, the applicant must be sure to submit a renewal request at least 30 days before the
expiration date of the license. If this deadline is met, the original license will remain in force
until the NRC acts on the request. This may take some time. During unusual periods when the
©2000 CRC Press LLC
Antimony 122
100 Antimony
10
Antimony 125 10
Arsenic 73 100
Arsenic 74 10
Arsenic 76 10
Arsenic 77
100
Barium 131 10
Barium 133 10
Barium 140 10
Bismuth 210 1
Bromine 82 10
Cadmium 109 10
Cadmium 115m 10
Cadmium 115 100
Calcium 45 10
Calcium 47 10
Carbon 14 100
Cerium 141 100
Cerium 143 100
Cerium 144 1

Cesium 131
1,000
Cesium 134m 100
Cesium 134 1
Cesium 135 10
Cesium 136 10
Cesium 137 10
Chlorine 36 10
Chlorine 38 10
Chromium 51 1,000
Cobalt 58m 10
Cobalt 58 10
Cobalt 60 1
Copper 64 100
Dysprosium 165 10
Dysprosium 166 100
Erbium 169 100
Erbium 171 100
Europium 152 (9.2 hr) 100
Europium 152 (13 yr) 1
Europium 154 1
Europium 155 10
Fluorine 18 1000
Gadolinium 153 10
Gadolinium 159 100
Gallium 72 10
Germanium 71 100
Gold 198 100
Gold 199 100
Hafnium 181 10

Holmium 166 100
Hydrogen 3 1000
Indium 113m 100
Indium 114m 10
Indium 115m 100
Indium 115 10
Iodine 125 1
Iodine 126 1
Iodine 129 0.1
Iodine 131 1
Iodine 132 10
Iodine 133 1
Iodine 134 10
Iodine 135 10
Iridium 192 10
Iridium 194 100
Iron 55
100
Iron 59 10
Krypton 85 100
Krypton 87 10
Lanthanum 140 10
Lutetium 177 100
Manganese 52 10
Manganese 54 10
Manganese 56 10
Mercury 197m 100
Mercury 197 100
Mercury 203 10
Molybdenum 99 100

Neodymium 147 100
Neodymium 149 100
Nickel 59
100
Nickel 63 10
Nickel 65
100
Niobium 93m 10
Niobium 95 10
Niobium 97 10
Osmium 185 10
Osmium 191m 100
Osmium 191 100
Osmium 193 100
Palladium 103 100
Palladium 109 100
Phosphorus 32 10
Platinum 191 100
Platinum 193m 100
Platinum 193 100
Platinum 197m 100
Platinum 197 100
Polonium 210 0.1
Potassium 42 10
Praseodymium 142 100
Praseodymium 143 100
Promethium 147 10
Promethium 149 10
Rhenium 186
100

NRC was under heavy work loads, it has taken over a year for action to take place.
Table 5.4 Exempt Quantities
Byproduct Material
::Ci
Byproduct Material
::Ci
©2000 CRC Press LLC

Table 4 Exempt Quantities, Continued
Byproduct Material
::Ci
Byproduct Material
::Ci
Rhenium 188 100
Rhodium 103m 100
Rhodium 105 100
Rubidium 86 10
Rubidium 87 10
Ruthenium 97 100
Ruthenium 103 10
Ruthenium 105 10
Ruthenium 106 1
Samarium 151 10
Samarium 153 100
Scandium 46 10
Scandium 47 100
Scandium 48 10
Selenium 75 10
Silicon 31 100
Silver 105 10

Silver 110m 1
Silver 111 100
Sodium 24 10
Strontium 85 10
Strontium 89 1
Strontium 90 0.1
Strontium 91 10
Strontium 92 10
Sulfur 35 100
Tantalum 182 10
Technetium 96 10
Technetium 97m 100
Technetium 97 100
Technetium 99m 100
Technetium 99 10
Tellurium 127m 10
Tellurium 127 100
Tellurium 129m 10
Tellurium 129 100
Tellurium 131m 10
Tellurium 132 10
Terbium 160 10
Thallium 200 100
Thallium 201 100
Thallium 202 100
Thallium 204 10
Thulium 170 10
Thulium 171 10
Tin 113 10
Tin 125 10

Tungsten 181 10
Tungsten 185 10
Tungsten 187 100
Vanadium 48 10
Xenon 131m 1000
Xenon 133 100
Xenon 135 100
Ytterbium 175 100
Yttrium 90 10
Yttrium 91 10
Yttrium 92 100
Yttrium 93 100
Zinc 65 10
Zinc 69m 100
Zinc 69 1000
Zirconium 93 10
Zirconium 95 10
While the license is in effect, the NRC has the right to make inspections of the facility, the
byproduct material, and the areas where the byproduct material is in use or stored. These
inspections have to be at reasonable hours, but they are almost always unannounced. The
inspector also will normally ask to see records of such items as surveys, personnel exposure
records, transfers and receipts of radioactive materials, waste disposal records, in strument
calibrations, radiation safety committee minutes, documentation of any committee actions,
and any other records relevant to compliance with the terms of the license and compliance
with other parts of 10 CFR, such as 19 and 20. Failure to be in compliance can result in
citations of various levels or of financial penalties. Enforcement will be discussed further later.
The NRC can require tests to be done to show that the facility is being operated properly,
such as asking for tests of the instruments used in monitoring the radiation levels, or
©2000 CRC Press LLC
ask the licensee to show that security of radioactive material in the laboratory areas is not

compromised.
Under Section 30.51, records of all transfers, receipts, and disposal of radioactive materials
normally must be kept for at least 2 years after transfer or disposal of a radioactive material, or
in some cases until the NRC authorizes the termination of the need to keep the records. There
are other record keeping requirements in other parts of Title 10.
If for any reason there is a desire to terminate the license on or before the expiration date,
Under 10 CFR 30.36 there are procedures that must be followed.
1. Terminate the use of byproduct material.
2. Remove radioactive contamination to the extent practicable (normally to background
level, see 5 below).
3. Properly dispose of byproduct material.
4. Submit a completed Form NRC-314.
5. Submit a radiation survey documenting the absence of radioactive contamination, or
the levels of residual contamination. In the latter case, an effort will be required to
eliminate the contamination.
a. The instruments used for the survey must be specified and then certified to be
properly calibrated and tested.
b. The radiation levels in the survey must be reported as follows:
(1) Beta and gamma levels in microrads per hour at 1 cm from the surface, and
gamma levels at 1 meter from the surface
(2) Levels of activity in microcuries per 100 cm
2
of fixed and removable surface
contamination
(3) Microcuries per rub in any water
(4) Picocuries per gram in contaminated solids and soils
6. If the facility is found to be uncontaminated, the licensee shall certify that no de-
tectable radioactive contamination has been found. If the information provided is
found to be sufficient, the NRC will notify the licensee that the license is terminated.
7. If the facility is contaminated, the NRC may require an independent survey acceptable

to the NRC. The license will continue after the normal termination date. However, the
use of byproduct materials will be restricted to the decontamination program and
related activities. The licensee must submit a decontamination plan for the facility.
They must continue to control entry into restricted areas until they are suitable for
unrestricted use, and the licensee is notified in writing that the license is terminated.
In principle, the NRC has the right to modify, suspend, or revoke a license for a facility
that is being operated improperly or if the facility were to submit false information to the NRC.
If the failure to comply with the requirements of the license and other requirements for safely
operating a facility can be shown to be willful or if the public interest, health, or safety can be
shown to demand it, the modification, suspension, or revocation can be done without
institution of proceedings which would allow the licensee an opportunity to demonstrate or
achieve compliance.
Normally, an inspection will be followed up with a written report by the inspector in which
a ny compliance problems will be identified. These may be minimal, serious (which would
require immediate abatement), or graduated steps between these two extremes. The facility
can (1) appeal the findings and attempt to show that they were complying with the
regulations or that the violation was less serious than the citation described or (2) accept the
findings. Unless the facility can show compliance, it must show how they will bring the
©2000 CRC Press LLC

facility into compliance within a reasonable period.
In recent years, there have been increasing numbers of occasions when the NRC has
imposed substantial financial penalties on research facilities, including academic institutions,
as they are entitled to do under Section 30.63, for violations that are sufficiently severe.
Further, a few years ago, one city filed 179 criminal charges against a major university and
several of its faculty members for failure to comply with radiation safety standards. Many
individual violations were relatively minor, but apparently the city attorney thought he had a
substantial case for a pattern of failure to comply with the terms of the license and the
regulations.
The use of radioisotopes in research is continuing to increase, while the public concern

about the safety of radiation continues unabated. It behooves all licensees to follow all
regulations scrupulously, not only to ensure safety, but also to avoid aggravating the
concerns of the public unnecessarily
1. Radiation Safety Committees
The primary function of the radiation safety committee (RSC), which is required under 10
CFR 33, is to monitor the performance of the users of ionizing radiatio n in a facility. It is, as
noted earlier, a local surrogate of the NRC or the equivalent state agency in an agreement
state. Usually, it is the ultimate local authority in radiation matters. In this one area at least, it
is assigned more authority than the usual senior administrative officials. It is an operational
committee, charged with an important managerial role in the use of ionizing radiation within
the organization, not in directly managing the research program but assuring that the research
is carried out safely. Due to this power, the NRC holds the committee responsible for
compliance and will cite the committee and the parent organization for failure to provide
appropriate oversight if the radiation users or radiation safety personnel under its supervision
fail to ensure compliance with the regulations.
In addition to the responsibility of the RSC to ensure compliance with the provisions of
the byproduct license and the other regulatory requirements of Title 10 CFR, it also must
establish internal policies and procedures to guide those wishing to use radiation and to
provide the internal operational structure in which this is done. The committee has other
duties as well, which will be discussed after the makeup of the committee is considered.
The membership of an RSC should be carefully se lected. It would be highly desirable to
select much of the membership from among the active users of radiation within the
organization and across the major areas or disciplines represented among the users. Each
prospective member should be scrutinized very carefully. A RSC must enforce regulations set
by one of the strongest regulatory agencies, and it must be fully willing to accept the
delegated authority. Individuals on the committee must be willing, if necessary to establish
policies that many users may feel are too restrictive. As active users themselves, they have a
better chance of achieving compliance if the other users realize that the members of the RSC
have accepted imposition of these same policies on their own activities. The members of the
committee should have a reputation for objectivity, fairness, and professional credibility. A

prima donna has no place on such a committee.
As professional scientists in their own right, the committee members will also understand
the impact of a given procedure or policy on labora tory operations, and can often find
legitimate ways to develop effective policies and procedures that are less burdensome on the
users to carry out than would otherwise be the case.
The radiation safety officer (RSO) of the organization must be part of the RSC, and is a
person who must maintain a current awareness of the rules and regulations required by the
NRC and of radiation safety principles. This individual will serve to carry out the policies of
the committee, and should be the individual to do the direct day-to-day monitoring of the
©2000 CRC Press LLC
operations of the laboratories using radioactive material. The decisions of the committee can
be burdensome not only on the users, but, without input of the RSO, can be equally
burdensome for this individual to carry out.
The working relationship between the RSO and the RSC is extremely important. No
committee can effectively administer a program of any size on a daily basis. It must delegate
some of its authority to a person, such as the RSO, or to an RSO through an alternate agency
such as a Safety and Health Department charged with the daily administration of the area of
responsibility assigned to an operational committee. However, especially when the RSO is a
dynamic, effective person there is a tendency to defer to this person and to abrogate some of
the committee
*s oversight responsibility. Both the RSC and the RSO should guard against
this possibility. The RSO should have a voice and an influential one in the committee
*s
deliberations, but should not be allowed to dictate policies independently.
The membership need not be limited to the persons already defined. A relatively new NRC
requirement is that a senior management representative must be an ex officio member of the
committee, and no official meeting can be held should the senior management represent-ative
not be present. This individual cannot veto the actions of the committee, but by being
present guarantees that higher management is aware of the actions of the committee. The
head of the health and safety department, if different from the radiation safety officer, may be

a member because this individual would bring in a wider perspective than would the RSO
alone on the implications of some issues brought before the committee. Some large organi-
zations may wish to have a representative of the organization
*s legal department as a member.
Some may wish to have a representative of the public relations area as a member, especially if
the facility is in an area in which there has been vigorous public opposition to the use of
ionizing radiation. Some may wish to include a layperson, if not as a voting member, then
perhaps as an observer, but the number of non-technical persons should not exceed those
with sufficient technical expertise to fully understand the safety issues. The membership
should not become too large, however, so that it will be practical to set up meetings without
too much concern for having a quorum. Committees that are too large also tend to be less
efficient, because of the time required for all the members to participate in discussions. On the
other hand, each major scientific discipline using radiation should be represented. A
reasonable size might be between 9 and 15 members, with a quorum established at between 5
and 8 members.
It is essential for the chair of the committ ee to be someone with prior experience with
radiation, but it is also highly desirable if the chair is an individual with administrative cre-
dentials. Such a person will normally ensure that committee meetings will be conducted
efficiently, but if the administrative experience is at a level carrying budgetary and personnel
responsibilities, the chair will bring still another dimension to the committee. Some actions of
the committee may carry cost or manpower implications; an individual with managerial
experience will recognize and perhaps have a feel for the feasibility of accommodating these
requirements.
Besides the monitoring of existing programs, establishing policies, and providing
guidance to radiation safety personnel, there are at least four other important functions that
the committee must perform. The first of these is to perform the same function as the NRC in
authorizing new participants to use radiation or radioactive materials. Basically the same
information that the NRC requires for new applicants for a license should be required when a
new internal facility is involved. The adequacy of the facility, the purpose of the program for
which the use of radiation is involved, and the qualifications of the users should all be

reviewed. At academic institutions especially there is a considerable turnover in users,
represented by graduate students, postdoctoral research associates, and even faculty. Often
individuals come from other facilities where internal practices may differ from local practices.
To ensure that all users are familiar with not only the basic principles of radiation safety but
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also with local internal procedures, a simple written test, administered as part of the
authorization procedure, is an effective and efficient means of documenting that the
prospective users have familiarized themselves with the information. To avoid setting
standards on who should take the test, it should be administered universally. Some faculty or
researchers may object, but it serves an important legal point. A passed quiz shows
unequivocally that the individual is familiar with the risks and the requirements associated
with the use of radiation at the facility. An argument frequently put forward by those who
object is that they are aware of the properties of the materials with which they are working,
and this is undoubtedly true. A rebuttal argument, however, is that they probably are not as
aware of the details of the NRC regulations with which they must comply and on the
compliance with which they, and the organization, will be judged by an NRC inspector.
An internal authorization should be issued to an individual. Others may be added to the
authorization, but one person should be designated as the local, ultimately responsible
person, responsible for compliance with applicable safety and legal standards related to the
use of radiation under the authorization. In laboratories that involve multiple users, it may be
necessary to formally identify a senior authorized user so as to provide the additional
authority to this individual.
The second additional function is to carefully review research or “new experiments,”
substantially different in the application of radioactive materials or radiation envisioned from
work previously performed under the license. This role is easy to play when it is part of a new
request for an authorization, but when an ongoing operation initiates a new direction in their
program, it will be necessary for the committee to make it clear that the user must address the
question to himself, “Is this application covered under the scope of work previously reviewed
by the committee in my application?” If the answer is no, or “possibly not,” then the

responsible individual should ask for a review by the committee. The need to do this must be
explicitly included in the internal policies administered by the committee. The RSC then must
consider the proposed program in the same context as the institution
*s application to the
NRC. Is the purpose of the work an approved purpose? This question must be answered
positively in the context of the NRC facility license. Are the facilities adequate to allow the
work to be done safely? Are the persons qualified because of training or experience to carry
out the proposed research program safely? Incidentally, it is not within the purview of the
committee
*s responsibility to judge the validity or worth of the research program, but only if
the proposed research can be done safely according to radiation safety and health standards.
Of course, obviously frivolous research is unacceptable for approval.
In the past, the use of proven research technology was sufficient to approve most
research and routine experiments did not receive the scrutiny that new experiments did. In the
last few years, the NRC has required the investigators to formally review even standard
procedures for possible hazards, to establish procedures to prevent these potential hazards
from occurring, and to develop a response protocol. Worst case failure mode s must be
reviewed. It is enlightening to see the results of these analyses. It is frequently found that
there is far more potential for failure than most would anticipate. The committee must review
and approve of these hazard analyses.
The fourth function not previously discussed is the role of the RSC as a disciplinary
body. Occasions will arise when individual users will be found to not be in full compliance
with acceptable standards. Often this will be done by the RSO in his periodic inspections, but
many will be reported by the users themselves. The NRC will expect these situations to be
evaluated and appropriate actions taken, which can include disciplinary measures. Not all
violations are equally serious. Categories of violations should be established by the RSC to
guide the RSO and the users. A single instance of faulty record keeping is not as serious as
poor control over byproduct material usage, for example. Allowing material to be lost or
©2000 CRC Press LLC