Technically
Speaking by Dr. John S. Nordin, PhD.
Detection of Radiation from Illicit
Materials
The release of dangerous
radioactive substances on civilian populations by a
terrorist as in a dirty bomb is one of the worst-case
situations short of a nuclear blast itself. AristaTek
has written an earlier article on “dirty bombs” and the
havoc that they may create (see March 2003
Newsletter, Technically Speaking). This newsletter
article looks at the problem of locating illicit
radioactive materials, of the type that might be used to
make a dirty bomb. Let us
first review some radiation basics.
Radiation
Basics
Of the approximately 200
different radioactive isotopes listed in the PEAC tool,
only a few stand out as being highly suitable for
radiological terror. These are cesium
137, cobalt 60, californium 252, strontium 90 (at its
short-lived daughter product yttrium 90), iridium 192,
radium 226, plutonium 238, and americium
241.
Example: Cesium
137:
Let us look at cesium 137 as
an example.
We will set the PEAC tool to read metric units,
go to “radioactive isotopes”, select “cesium 137” or “Cs
137” and look at the PEAC tool display. Sometimes
cesium 137 is written as 137Cs. The number
“137” is the sum of the number of protons (55) plus
neutrons (82) in the nucleus of the cesium atom. The atomic
number (55) is the number of protons. An atom
must have the right number of neutrons and protons to be
stable.
If there are too few or too many neutrons for the
number of protons, the atom will shed some of its excess
mass (in the form of alpha or beta particles or even
neutrons depending upon the radioactive isotope). In the process
of shedding mass, a minute portion of the atom mass will
be converted to energy. In the
case of Cesium 137, much of this energy will be
converted to gamma radiation with an energy level
of 0.6616
MeV
(million electron volts). A beta
particle will be ejected from the nucleus, which will
have a kinetic energy of up to 1.176 MeV. The beta
particle has a mass (same mass and charge as an
electron) and will slow down and eventually stop as it
interacts with the surrounding air. The
maximum travel distance of the beta particle from the
Cesium 137 source can be calculated (e.g. 419 cm in air
at sea level). On the
other hand, gamma radiation has no mass and can travel
much further.
Theoretically, gamma radiation can travel an
infinite distance in the vacuum of outer space. If there
is some material in the way, the gamma radiation will
eventually be absorbed as it penetrates the
material.
Cesium 137 has a half life of
30.2 years.
This means that if there is a canister containing
some cesium 137, half of the cesium 137 will be gone
after 30.2 years. The cesium
will be converted to barium 137, which is stable,
meaning that there is no further radioactive decay. A barium 137
atom contains 56 protons and 81 neutrons. One of the
neutrons of the cesium 137 atom has been converted to a
proton and a beta particle plus energy (kinetic energy
of the expelled beta particle plus the gamma radiation)
to give barium 137. When
barium 137 is initially formed (designated barium 137m,
with a half life of 2.55 minutes), some x-rays are given
off before forming the stable isotope barium 137. We can’t predict
when an individual atom of cesium 137 will undergo
radioactive decay, but a few milligrams of cesium 137
will contain many billions of atoms and half of these
will be converted to the stable (non-radioactive) barium
137 after 30.2 years.
The PEAC tool display shows
cesium 137 has a radiation activity of 86.7 curies per
gram.
Radiation activity can be calculated directly
from the half-life, e.g.
Radiation activity =
1.31(10)8 /[ (half-life in days) ( # of
protons + neutrons)]
For Cesium 137,
Radiation activity = 1.31(10)8
/[(30.2)(365)(137)] = 86.6912 Ci/g
Sometimes radiation activity
is expressed in Becquerels (Bq). To convert
Curies to Becquerels, multiply by 3.7(10)10
.
People have asked, what does
cersium 137 look like? Is it a
powder and what color is it? How can I
recognize it?.
Cesium 137 looks like any other chemical. It may a powder,
an aqueous solution, a solid, or mixed with other
chemicals.
It may be in the form of cesium chloride (CsCl),
cesium fluoride (CsF), cesium sulfate
(Cs2SO4), cesium hydroxide (CsOH)
or some other chemical. The only
way of detecting it is by the radiation given off, in
particular, gamma radiation with an energy level
approximately equal to 0.66 MeV. A first
responder investigating a mysterious package or canister
might be tipped off if the package is unusually heavy
for its size because of lead shielding, but there is no
guarantee that a terrorist will adequately shield the
package.
The radiation given off would cause the canister
to feel warm to the touch, but by that time the
responder would already have been exposed to dangerous
radiation.
Example Cobalt
60:
Let us look at Cobalt 60 (or Co 60) in
the PEAC tool.
A Cobalt 60 atom has a nucleus with 27 protons
and 33 neutrons. The half
life of cobalt 60 is 5.271 years. When a cobalt 60
atom undergoes radioactive decay, a neutron is converted
to a proton and a beta particle and a very small amount
of mass is converted to energy. The energy
shows up in part as kinetic energy of the beta particle,
which is ejected from the atom, and partly as gamma
radiation.
Each atom disintegration produces gamma radiation
at two energy levels, 1.1732 MeV and 1.3325 MeV. If a
responder had a gamma radiation detector capable of
measuring gamma radiation at different energy levels and
measured radiation at 1.1732 MeV and 1.3325 MeV, some
cobalt 60 would be expected to be nearby. The cobalt 60
atom undergoing radioactive decay is converted to nickel
60, which is a stable atom and does not undergo further
radioactive decay. Nickel 60
has 28 protons and 32 neutrons.
Example Californium
252:
The PEAC tool display for
Californium 252 (or Cf 252) shows that a lot of things
happen with this radioactive isotope as it undergoes
radioactive decay.
A californium 252 atom contains 98 protons and
154 neutrons.
The half life of Californium 252 is 2.65
years.
Most (96.9%) of the atoms undergoing radioactive
decay shed a mass equal to two protons and two neutrons
(called an alpha particle, or alpha radiation) from the
atom nucleus forming curium 248. The curium
248 nucleus has 96 protons and 152 neutrons, and also
undergoes further radioactive decay. The other
(3.1%) of the atoms of Californium 248 undergo
spontaneous fission, that is, the atom splits apart
forming smaller fragments.
There are many different ways that Californium
248 can split into smaller atoms. These fragments
are also radioactive, that is, they may shed alpha and
beta particles plus more gammas radiation. During the
fission process itself, neutrons and beta particles will
be expelled from the atoms plus accompanying gamma
radiation.
Neutrons can travel far from the source and can
inflict severe damage to the human body. Prompt
gammas refer to gamma radiation emitted at the time the
atom undergoes fission; delayed gammas refer to later
gamma radiation.
Almost all (99+%) of the neutrons emitted at the
time the atoms undergoes fission are prompt, that is,
they are emitted at the time of fission. Very few
(<1%) are delayed.
If cerium 248 is pulled up on
the PEAC tool, the display shows a half life of 340000
years. When
cerium 248 undergoes radioactive decay, 92% of the atoms
shed an alpha particle producing plutonium 244 and the
other 8% undergo spontaneous fission producing various
smaller atom fragments, neutrons, gamma radiation, and
beta particles.
Plutonium 244 has a very long half life (82
million years), but eventually it too will shed an alpha
particle (99.9% of the atoms) producing uranium 240; a
small fraction (0.1%) will undergo spontaneous
fission.
Uranium 240 has a short half life (14.1 hours)
shedding a beta particle producing neptunium 240, and
then plutonium 240, and so on, until stable elements are
eventually produced many millions of years
later.
What Does
Radiation Basics Tell
Us?
Two things given off by
radioactive materials can be measured by detection
equipment located at a distance. One is
gamma radiation, the other is neuron particle
radiation.
Gamma radiation is given off by radioactive
isotopes, which can be used to make a dirty bomb. Neutron
radiation is given off by certain heavy radioactive
isotopes (atomic number 92 or greater) undergoing at
least some fission, and could mean the presence of ingredients to
make a nuclear bomb. These heavy
radioactive isotopes also give off gamma radiation.
Alpha and beta particles do
not have enough kinetic energy to travel from the
source. Alpha particles can travel at best only a few
centimeters and beta particles only a few meters in
air.
Gamma radiation and neutrons do not have that
restriction.
Some of the natural gamma radiation reaching the
earth originated from galaxies millions of light years
away.
Gamma and neutron radiation
decrease inversely approximately as the square of the
distance from the source. This means
for example there is a flux of a million neutrons per
square centimeter (or a million gamma photons per square
centimeter) at a ten meters distance from the source,
there would be approximately 10,000 units per square
centimeter 100 meters from the source. The word
“approximately” is used rather than “exactly” because
some scattering takes place as the radiation travels
through the air.
Another thing radiation
basics tell us that each radioactive isotope is
different.
The various energy levels associated with gamma
radiation represent a signature for that isotope
allowing it to be identified. Mixtures of
several radioactive isotopes will be more difficult to
identify, but even these may have recognizable
signatures at distinct gamma energy
levels.
Gamma and Neutron
Signatures
Let us look at some gamma
and neutron radiation measurements that might be
recorded by a monitoring system. The
detection systems for gamma radiation and neutrons are
different so we will look at gamma radiation first. Gamma
radiation detectors are available which simply give a
total count rate, but we will look at a system that
gives the total gamma-ray spectrum as a function of
energy level. This will
help in identifying of the radioactive isotopes and to
distinguish between the target illicit material and
natural radiation background.
Figure 1 shows a
hypothetical tracing of what background radiation might
look like for a detector allowed to record counts at
different energy channels [1000 KeV = 1
MeV] for some specified period of time. The
natural radiation comes from many sources, the rocks and
soils of the ground, building materials, radiation from
outer space, and some minute residuals from nuclear
tests conducted decades ago.
Figure 2 shows a plot at the
same location and for the same time period but with some
cobalt 60 located perhaps 100 meters
away. The increased counts at energy
levels near 1.173 and 1.333 MeV represent a signature
for cobalt 60.
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Recall that gamma radiation
decreases inversely as the square of the distance from
the source.
As the detector moves further from the cobalt 60
source, the cobalt 60 counts will blend into
background.
But if the detection system does identify peaks,
the instrumentation system can be set to measure counts
at these energy levels and move into the
source.
If the detection system only
measured the total gamma count summed over at all energy
levels, it probably would not be sensitive enough to
make a distinction from background unless it moved in
relatively close to the source. Being able
to rapidly measure gamma radiation at different energy
levels allows for better distinction from background at
greater distances.
This is important in the detection of illicit
materials which may be hidden and partially
shielded.
In the case of neutron
radiation, natural background neutron radiation is
extremely low.
Therefore the neutron detector need only measure
the total neutron count rather than consider neutrons at
different energy levels. For example, the
total neutron count per unit time reaching a detector
say 30 meters away from 0.000001 grams of Californium
252 will still be several times background, and could be
picked up by an appropriate detector. As the detector
moves in closer, the count rate should go up by roughly
a factor of 100 as we moved in by a factor of 10. Again, the
neutron flux varies approximately as 1/r2
where r is the distance from the source. The relationship
is approximate because of neutron scatter in the air and
from the ground.
A description of a
vehicle-carried gamma and neutron detection system is
available at http://www.ortec-online.com/papers/cartop_inmm04.pdf. The
system described is the ORTEC NaI-SS Portable Search
System, available at a cost of $68,600 (as of February
2005).
ORTEC (Oak Ridge, TN) is a subsidiary of
AMETEK, Inc.
The system is designed to operate in a moving
car. The
paper at the website presents drive-by test results for
Cesium 137 and Cobalt 60 gamma radiation sources and
Californium 252 neutron sources. The system
also includes a Global Positioning System (GPS) to
determine its location while each spectrum and count is
collected.
Shielding
- Gamma Radiation. Denser
materials, especially lead, are most effective in
reducing gamma radiation from the source. A lead shield
does not stop the radiation but only reduces it. Higher
energy gamma radiation are more likely to pass through
shielding than lower energy gammas. From a
practical standpoint, this means that the detection
equipment must move in closer to the source to detect
radiation from background.
- Neutron radiation. While
more dense materials are generally more effective in
reducing neutron radiation, there are also many
exceptions.
The neutrons interact with nuclei of any
intervening material; the neutrons may either be
absorbed by the nuclei or scattered by the nuclei of
the material.
Some of the energy produced as the result of
the collisions may be emitted as gamma radiation. Certain
elements, in particular boron 10, are rather effective
in slowing down neutrons. The mineral
colemanite, which has a high proportion of boron, may
be incorporated into concrete as an effective
shielding material. Gamma
radiation with energy 0.48 MeV is produced as the
result of interaction with boron 10. The
addition of iron and/or barium to concrete also
attenuates neutrons. Again,
from a practical standpoint, shielding means that the
detection equipment must move in closer to the source
to detect neutrons.
How Safe Is It to Approach
Radioactive Materials?
We will look at
gamma and neutron radiation only. Alpha and beta
particles carry a charge and can travel only a finite
distance, which is a function of their kinetic energies
only. Alpha
particles will be stopped by the canister containing the
radioactive material. Beta
particles can easily be contained by shielding. Gamma
photons and neutrons can travel much
further.
There are a couple of ways of
estimating of how safe it is to approach a canister
containing a radioactive material.
·
If
the radioactive material is identified and the quantity
is known (e.g. 100 microcuries of Californium 252; 10
grams of Cesium 137, etc.), the gamma and neutron
radiation flux can be calculated as a function of
distance from the source. The flux is
calculated at each energy level. Once the
fluxes are known, the fluxes are converted to dose (in
units of rems or sieverts).
·
If
the radioactive material has not been identified and the
quantity is not known, detection equipment capable of
measuring neutron radiation and gamma radiation is
necessary. The
gamma radiation detector should be capable of measuring
the gamma radiation at different energy levels. The gamma
radiation signature may allow identification of the
radioactive material at a distance without going near
the source.
Once the radiation count at various energy levels
is measured at a at least a couple of locations plus
background, the fluxes are calculated, and the fluxes
converted to dose.
As a rough rule of thumb, the
dose due to normal background radiation at an
uncontaminated site is about 150 mrems per year [1000 mrem = 1
rem].
Special circumstances such as use of some
granites in building materials, a high elevation site,
or radon gas exposure in some buildings could boost
background radiation dose another 50 to 400 mrems per
year.
The U.S. National Council on Radiation Protection
(NCRP) recommends the an annual whole body exposure
limit of 5 rem in one year for workers in the nuclear
industry, or an accumulated whole body exposure for
adults of [(age in years – 18) x 5 ] rems above normal
background.
Dose is accumulative, meaning, if a person
receives an 1 rem dose from a radioactive source in one
incident plus another 1 rem dose from another incident
one year later, the total dose is 2
rem.
The PEAC tool contains
information relating dose to adverse effects such as
increased risk of cancer, radiation sickness, and
probable death.
The calculations for
computing radiation fluxes and dose are very
complex.
We can give only a rough outline of the steps
involved and present some answers for a couple of
radioactive isotopes. A basic starting
step is the equation relating flux (number of gamma
photons or neutrons per square meter per second) at
distance d from the source to the number released per
second, e.g.
Flux = S/(4πd2)
where S = source strength
(number of neutrons or gamma ray photons per
second)
d = distance from the source,
meters
The above equation is true
for a vacuum. In an
actual situation there will be air and other materials
between the source and location at distance d.
Various factors must be added to the equation to
account for this.
Flux = B S e-μd
/(4πd2)
B = buildup factor,
dimensionless
μd = number of mean free
paths, dimensionless
The flux must be computed
separately for each gamma photon energy level. A similar
expression is used for neutrons at each energy
level.
Values for B and μd are calculated from other
mathematical expressions and lookup tables [such as in
Appendix D and E of N. Tsoulfanidis, 1983,
Measurement and Detection of Radiation, McGraw
Hill].
When we get done, we get a table of fluxes of
gamma radiation and neutrons at various energy levels at
distance d from the source. The fluxes
are then converted to rems (or sieverts) using tables
in
“Neutron and Gamma-ray
Flux-to-Dose Rate”, American National Standard,
ANSI/ANS-6.11-1977. The
rems (or sieverts) are summed for each energy level to
get a total dose.
If the amount of radioactive
material is known, the source strength can be
calculated.
Conversely, if the fluxes can be measured at
several locations using detection equipment, the source
location can be pinpointed, the radioactive isotope
identified from its energy signature, and the source
strength estimated. This will
help in providing an estimate of safe approach. The PEAC tool
gives the number of curies per gram of material from
which the number of disintegrations can be calculated [1
disintegration per second = 1 Bq = 2.703 x
10-11 curies]. The intensities
in the PEAC tool give the percent of
disintegrations that result in gamma radiation of that
energy level.
For example, the flux of
gamma photons from 1 gram of Cesium 137 at a distance of
10 meters in air is 2.7543 (10)9
photons/m2-s. This
converts to a dose of 0.402 rem/hr. There is
only one gamma energy level to consider (0.66 MeV) and
no neutron emissions.
The calculations for 1 gram
of Californium 252 are much more complex. Gamma
radiation at various energy levels plus neutron
radiation also at various energy levels (up to about 13
MeV) are emitted. Each
energy level must be separately calculated. When we
are done, the dose received by a person located 10
meters away is calculated to be roughly 30 rem/hour
(roughly, because neutron scatter from surrounding
materials and the ground results in some uncertainty in
the calculations).
At 100 meters away, the rem
dose for the cesium 137 example would probably be on the
order of 0.004 rem/hour. For the
californium 252 example, the dose at 100 meters might be
on the order of 0.3 rem/hour.
With a background dose of say 0.3 rem/year [=
0.0000342 rem/hour], detection equipment located 100
meters away should be able to measure these materials
remotely, assuming that the source has minimal
shielding.
Example
Radiation Detectors (assembled
February 2005)
RAE Systems. AreaRAE
Gamma.
Multi-gas and Radiation Monitor. Total gamma radiation
count between 0.06 MeV and 3 MeV.
Scintillation crystal detector.
Approximate cost $3500. Specifications
at http://www.raesystems.com/~raedocs/Data_Sheets/AreaRAE_Gamma.pdf
GammaRAE II. Total
Gamma radiation count. Cesium iodide
scintillator.
Cost $1000.
See http://www.energyvortex.com/pages/headlinedetails.cfm?id=1616.
NeutronRAE Pager. Total gamma or
neutron counts.
Gamma count between 0.033 and 3 MeV, neutron
count between thermal and 14 MeV. Cesium Iodide
and lithium iodide scintillators. Cost about
$3300.
Details at http://www.calcert.com/pdf/NeutronRAE_pager.pdf.
http://www.mlu.at/en/instruments/neutronrae_pager_e.html.
SAIC (Canada)
GR-110G Handheld Survey Gamma Radiation Detector. Total gamma
radiation count between 0.045 MeV and 3 MeV.
Sodium iodide detector.
Specifications at http://www.saic.com/products/security/gr-110/gr-110-tech.html.
POLISMART Instruments. Several
personal gamma radiation monitors. PM1801 model
allows accumulation of gamma MeV spectra for isotope
identification.
Cesium iodide detector. Looks like an
oversized cell phone. Details at
http://www.energyvortex.com/pages/headlinedetails.cfm?id=1616.
Gamma-neutron PRD & RIID
PM1802 detector for gamma and neutron radiation at http://www.polismart.com/model2.htm.
Technical details for PM1402
monitor at http://polimaster.com/download/pm1402mom.pdf.
Polimaster, Inc.. Alexandria
VA. Various
gamma and neutron radiation detectors. Details at http://www.polimaster.com/ENGL/tech_dev/1402_E.htm. General
website http://www.polimaster.com/index.html. Some also
available through RAE Systems,
Inc.
D-tect Systems., Division of
Mission Research Corporation. Gamma
radiation detector useful for detection of gamma
radiation in luggage, packages, or setup at
doorways.
Sodium iodide detector with Thallium
scintillator. Cost about
$10000.
Details at http://www.usascan.com/pdf/rad-d.pdf. Detector
measuring gamma energy spectra for remote identification
of isotopes:
http://www.dtectsystems.com/dtectdocs/rad-ID%20specs.pdf
.
StarDot Technologies
(California). Remote gamma
radiation detection equipment.
http://www.stardot-tech.com/media/stardot_pr_radnetcam.pdf. Information and
images
from
stationary detectors sent via Internet to
authorized users.
Aspect Scientific
Production
Center
(Russia). Gamma radiation
and neutron detectors. http://aspect.dubna.ru/english/page.php?page=342.
Sensor Technology
Engineering.
Small hand-held gamma ray and thermal neutron
monitor mentioned by DOD (TSWG) for use by first
responders. http://www.tswg.gov/tswg/tos/tos_currpr.htm.
Inovative MicroSensors,
Inc.
Gamma and neutron radiation detector chips and
detectors.
Various costs up to about
$11,000.
Details at http://www.ia-tec.com/Security/BSU3.pdf.
Synodys (MGP Instruments
Inc., Smyma Georgia) PDS100GN pocket
sized personal gamma and neutron radiation
detector.
http://www.army-technology.com/contractors/nbc/synodys/synodys4.html.
ORTEC, Oak Ridge,
TN. Gamma and
neutron radiation source detector. Idendifies
radioactive isotope by energy spectra. http://www.ortec-online.com/pdf/detex.pdf.
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