An Introduction to Radiation Protection An Introduction to Radiation Protection 6e 2012 Martin Harbison Beach ColeCRC Press Introduction Properties of Radionuclides Analysis Techniques ID: 792747
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Slide1
Practical Health
Physics Techniques
An Introduction to Radiation Protection
An Introduction to Radiation Protection 6e © 2012 Martin,
Harbison
, Beach, Cole/CRC Press
Slide2Introduction
Properties of Radionuclides
Analysis TechniquesEnergy determination
Measuring half livesGross alpha and beta counting
Leak testing sealed sourcesAn Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide3Properties of Radionuclides
Radionuclides emit radiation of a specific type and energy, a bit like having their own fingerprint
For example:
Co-60 emits 0.31 MeV β-, 1.48 MeV β-
, 1.17 MeV γ, 1.33 MeV γ and has a half life of 5.27 yearsSr-90 emits 0.56 MeV β- and has a half life of 28.8 yearsAm-241 emits 5.443 MeV α, 5.486 MeV α, 59.5 keV γ and has a half life of 432.2 yearsAn Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide4Identification of Radionuclides
Identification of an unknown radionuclide can be achieved by determining:
the type and energy of radiation that it emits and/or
its radioactive half lifeComparing this information against reference data for all known radionuclides allows the identity of an unknown radionuclide to be determined
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide5Energy Determination
Gamma spectrometry - easy and convenient method (see Chapter 7)
Alpha spectrometry - much less common than gamma spectrometry and generally involves a significant amount of sample preparation
Beta absorption methods – can be carried out easily with limited equipment, if access to a gamma spectrometer is not possible to access a gamma spectrometer or the radionuclide is a pure beta emitter An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide6Beta Absorption Method 1
Count the sample in a beta counting system e.g. GM detector in a lead castle
Measure the count rate with increasing thicknesses of aluminium between the sample and the detector
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide7Beta Absorption Method 1
Draw an absorption graph by plotting count rate (background corrected) against absorber thickness (expressed in g/cm
2
) on log-linear paper
Compare result with curves for various known β energies and identify the one which aligns with plotted results
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide8Beta Absorption Method 2
Count the sample in a beta counting system e.g. GM detector in a lead castle
Measure the count rate with increasing thicknesses of aluminium between the sample and the detector until the count rate has reduced to about one quarter of the initial value
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide9Beta Absorption Method 2
Plot count rate (background corrected) against absorber thickness (expressed in g/cm
2
)
Determine the thickness that would reduce the count rate to one half – the half-value thickness (HVT)In this case the HVT is 0.074g/cm2
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide10Beta Absorption Method 2
Determine the beta maximum energy by reading off a HVT-beta energy graph for the absorber used (in this case aluminium)
Maximum beta energy is
1.4 MeV
This corresponds to sodium-24 which has a maximum beta particle energy of
1.39 MeV
0.074g/cm
2
1.4 MeV
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide11Issues with Identifying Nuclides by Determining the Maximum Beta Energy
Difficult to do in practice as likely to be more than one nuclide and consequently several beta energies present
Difficult to identify nuclides solely from information about maximum beta energies
Can be used as a piece of the identification jigsaw, alongside other methods such as determination of half lifeAn Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide12Determination of Half Life
The activity of a nuclide at time t (A
t
) is given by:
where A
0
is the activity when t=0 and T
1/2
is the half life
Take a series of counts at suitable intervals (such that the count rate decreases by 10-15% between counts)
Plot the corrected count rate against time on a log-linear scale. The half life can then be determined from the graph by assessing the time it takes for the count rate to reduce by half
Alternatively, the half life can be determined statistically as shown on the next slides
=
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide13+
Determination of Half Life
Time (h)
0
2
4
8
12
18
Count rate (cpm)
6720
6050
5690
4563
3930
2989
Plotting the log
e
of the count rate against the time gives the following graph
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide14Determination of Half Life
Hence the gradient of the graph is equal to
–
λ
The gradient of the graph is
-0.0449
using linear regression
Therefore
= 15.4 hours
A nuclide with a half life of 15.4 hours is
Na-24
Rearranging gives
and rearranging further gives
Now
=
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide15Issues with Identifying Nuclides by Determining the Half Life
Only suitable for nuclides with half lives between a few minutes and a few months
Difficult to do in practice as likely to be more than one nuclide present
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide16Identifying a Nuclides when another short lived Nuclide is present
This is the decay plot of Na-24, although there is also a shorter lived nuclide present
Rate of total decay decreases to eventually give a straight line when only the longer lived nuclide remains
Extrapolate the straight line back to t=0. Use the revised line (shown in green) to determine the half live of the longer lived nuclide. Time taken for count rate to reduce from 1000
cpm to 500
cpm
is about 15 hours (actual nuclide is Na-24 with a half life of 15.4 hours)
Extrapolation of long lived nuclide
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide17Produce a decay plot for the short lived nuclide by deducting the contribution of the longer lived nuclide count rate (using the extrapolated line) from the total count
rate
Use this decay plot (red line) to determine the half live of the shorter lived nuclide. Time taken for count rate to reduce from 2000 counts/min to 250 counts/min (3 half lives) is about 2 hours, giving a half life of about
40 minutes (actual
nuclide is
Cl-38
with a half life of
37.3 minutes)
Identifying a Nuclides when another short lived Nuclide is present
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide18Gross Alpha and Beta Counting
Generally done with a high sensitivity counting system
Can use an alpha detector (drawer assembly) or beta detector (drawer assembly or in a beta castle)
where
C
c
= background corrected count rate in cps and
E
c
= percentage counting system efficiency
Power supply
Detector
Amplifier
Discriminator
Scaler
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide19Gross Alpha and Beta Counting
Efficiency
is defined as the fraction of particles counted compared with the total number emitted
It is determined by measuring the count rate from a source of known emission rate in the counting position to be used for the samples to be counted (i.e. same shelf if a beta castle is used)
Example
If the known source activity is 220
Bq
its emission rate will be 220 x 60 = 13200
dpm
. If it gives a corrected count rate of 1980
cpm
the detector efficiency will be
Efficiency (%) =
x 100
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide20Gross Alpha and Beta Counting
Example
Calculate the activity of a source which gives an uncorrected count rate of 4925
cpm
in a detector which has an efficiency of 15% and gives a background count rate of 65
cpm
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide21Counting a Smear Sample
where
C
c
= background corrected count rate in
cps
E
c
= percentage counting system
efficiency
A = area smear in cm
2
and
E
F
= percentage of the contamination picked up by the smear paper
Note: E
F
is difficult to determine and is dependent on physical and chemical nature of contamination, nature of the surface being smeared etc. It is usually assumed to be 10%, but could be as high as 100%
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide22Counting an Air Sample
where
C
c
= background corrected count rate in
cps
E
c
= percentage counting system
efficiency
V = volume of air sampled in m
3
Note: Take care when interpreting results as radon daughters may be present. Allow the sample to decay for 24 hours and then recount if the presence of radon daughters is suspected. Consider using radon compensating counters in areas where radon is known to be present
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide23Issues with Gross Alpha and Beta Counting
Need to correct for resolving time of counter (see later)
Efficiency is dependent on:
Geometry of the counting system
Backscatter
Self absorption in the source
Absorption in the counter window
Absorption in the air gap between the source and detector
Many of these factors are dependent on the energy of the radiation & hence the efficiency is energy dependent
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide24Issues with Gross Alpha and Beta Counting
Ideally the counter should be calibrated with a source of the same nuclide and the same geometry as the samples to be counted
Not practicable to calibrate the counter for range of energies
For health physics purposes it is usual to calibrate with one typical source and accept possible errors when assessing nuclides of other energies
However, this error can be particularly significant for some nuclides e.g. low energy beta emitters, so corrections may need to be made
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide25Corrections for Resolving Time
Resolving time
is the short period of time (order of 100 µs) after a
α
or
β
particle or
γ
photon has just been detected that other particles/photons cannot be detected
It is the time required for the charged particles generated by the interaction of the ionising radiation in the detector to be collected
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide26Corrections for Resolving Time
Sometimes referred to as the
dead time
of the detector because during this time it cannot respond to any new event
A
fixed dead time
, which is a function of the circuitry, can be introduced into the counting system
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide27Corrections for Dead Time
The dead time can be corrected for dead time by the following equation
where
C
=
true count rate in cps
c = observed count rate in cps
t
=
dead time in s
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide28Corrections for Dead Time
Example
Calculate the true count rate of a sample if the observed count rate is 500 cps and the dead time is 200 µs
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide29Counting Statistics
Radioactive decay is a
random
process
The number of counts in a given time will fluctuate around an average value
The
standard deviation
σ
,
is a measure of the scatter of the counts about their average value
If the average of a number of counts is
N
, the standard deviation is
√
N
If N = 900 counts,
σ
=
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide30Counting Statistics
If a count is taken over time t and N counts are recorded:
Example
A 10 s count gives a result of 400 counts. What is the count rate and standard deviation?
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide31Counting Statistics
68% of the observations are within one standard deviation of the true count rate i.e. for the previous example there is a 68% chance that the count rate is between 38 cps and 42 cps
The standard deviation is a measure of the accuracy of the measurement
Greater accuracy can be achieved by increasing the total count recorded
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide32Counting Statistics
Example
100 counts in 5s: count rate = 20 ± 2 cps
1000 counts in 50s: count rate = 20 ± 0.63 cps
10000 count in 500s: count rate = 20 ± 0.2 cps
The standard deviation can also be expressed as a percentage.
N=100,
σ
= 10 (10%)
N= 1000,
σ
= 31.6 (3.2%)
N= 10,000,
σ
= 100 (1%)
To be accurate to 1% the counting period must be long enough to give at least 10,000 counts
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide33Counting Statistics
The background corrected count rate S, is given by:
where
N is the total count rate (with background) in time t
1
B is the background count in time t
2
and
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide34Counting Statistics
Example
A
5 minute count gave
a result of
5325 counts. The background count in 10 minutes was 267 counts. What is the corrected count rate and the standard deviation?
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide35Counting Statistics
For low activity sources long count times will be required to achieve an acceptable accuracy
Need to choose the most efficient split of time between the sample count and the background count
Highest accuracy is achieved when
where
t
1
is the sample count time
t
2
is the background count time
k is the ratio of the sample count rate to the background count rate
Need to do a short count first to determine the count rates and hence determine the value of k
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide36Counting Statistics
Example
Sample count rate is about 320
cpm
and the background count rate is 20
cpm
. A total of 10 hours count time is available. How much time should be spend counting the background?
Therefore sample count time should be 4 times the background count time
ie
the background should be counted for 2 hours (and the sample for 8 hours)
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide37Leak Testing Sealed Sources
Sealed sources should be leak tested at regular intervals (in UK generally every two years)
Risk assessment should determine most appropriate method – either
direct smearing of the
source
or indirectly (
if source is inaccessible or wiping it could damage the integrity of the source) e.g. by smearing the surface of the source
container. You
might also need to use shielding or source handling tools
etc
Pass/fail criteria should be specified
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide38Leak Testing Sealed Sources
Smear paper should be assessed in a suitable counter to determine the presence of any radioactive material, at levels below the pass/fail criteria, that has leaked from the source
Records should be maintained
Further information in ISO 9978: Sealed Radioactive Sources – Leakage Test Methods
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide39Summary (1)
Identification of Nuclides –
can be by
α, β or γ spectrometry,
β absorption or half life measurementsDetermination of Sample Activity – need to know counting efficiency, taking into account energy of radiation and also the radiation backgroundSurface Contamination Level
Airborne Contamination Level
An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press
Slide40Summary (2)
Resolving Time –
time that the detector is unable to detect radiation after it has registered a pulse. Reduces effective counting time. More significant for higher count rates
Counting Statistics – standard deviation (σ
) is a measure of the accuracy of a count. . More counts gives better accuracy e.g. 10,000 counts gives 1% accuracy. Accuracy is also affected by the background count rate An Introduction to Radiation Protection 6e © 2012 Martin, Harbison, Beach, Cole/CRC Press