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Topic 4' Problems in Radiation Detection and Measurement

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Detection efficiency depends on a number of factors: absorption and scatter (F) ... pulse rates (Pt) are generated (pulse hight larger than the photo-peak) and the ... – PowerPoint PPT presentation

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Title: Topic 4' Problems in Radiation Detection and Measurement


1
Topic 4. Problems in Radiation Detection and
Measurement
  • Detection Efficiency
  • Problems in the detection and measurement of beta
    particles
  • Deadtime

2
Detection Efficiency
  • The Definition
  • Geometric Efficiency
  • Intrinsic Efficiency
  • Energy Selective Counting
  • Absorption and Scatter

3
The Definition
  • Emission Rate (assume ? rays per disintegration)
    ?(?rays/sec)3.7104(dis/µCi.sec) A(µCi) ?
    (?rays/dis)
  • Detection Efficiency (with R the recorded
    counting rate) DR/ ?

4
Detection Efficiency
  • Detection efficiency depends on a number of
    factors absorption and scatter (F), geometric
    efficiency (g), intrinsic efficiency (e) and
    energy-selective counting (f).
  • It can be expressed as DFg e f

5
Geometric Efficiency
  • Inverse square law I?/4pr2 where I is the
    intensity of radiation per unit area and ? is the
    source emission rate.
  • For point source, geometric efficiency is
    gpa/4pr2 where a is the detector surface area
    and r is the distance from the point source.

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Geometric Efficiency (small distance r)
  • Assume the detector is close to the source (small
    r), the area of the detector is SOr2 where
    O2p(1-cos?).
  • The geometric efficiency is then
    gpS/4pr2Or2/4pr2(1-cos?)/2
  • When source in contact with the detector ?90o,
    gp1/2 and when source is immersed in the
    detector material, ?180o, gp1.

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10
Intrinsic Efficiency
  • Intrinsic efficiency is defined as e(no. of
    radiation interacting with detector)/(no. of
    radiations striking the detector)
  • For ?-ray detector, eIo-Ioexp-µl(E)x/Io
    1-exp-µl(E)x where Io is the incoming ?-ray
    intensity and Ioexp-µl(E)x is the ?-ray
    intensity that pass through the detector without
    interaction.

11
Effect of ? ray energy and detector thickness on
Intrinsic Efficiency
  • For NaI(Tl) detector, the intrinsic efficiency
    increases with the increase of thickness x and
    decreases with the increase of the photon energy
    (x5cm, for most nuclear medicine energy, e1)
  • For semiconductor detector, the intrinsic
    efficiency is also energy dependent (comparison
    with NaI(Tl) is complicated due to the coupled
    atomic number and the crystal density)

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13
Intrinsic Efficiency (gas filled detectors)
  • For gas filled detectors, the intrinsic
    efficiency is very small for photons (?, X, e
    lt0.01) but good for particle radiations (a,ß,
    e1).
  • Detection of ? rays by gas filled detectors is
    mostly via electrons knocked out from the wall by
    the ? rays.

14
Energy Selective Counting
  • Not all output signals are counted in energy
    selective counting
  • Photo-fraction fp is defined as the ratio of the
    counts in the photo-peak over the signal counts
    produced by the detector.
  • Photo-fraction depends on ? energy, detector
    material and detector size.
  • Full spectrum counting provides the maximum
    possible counting rate (used for single
    radionuclide with small scattering).

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16
Non-uniform Detection Efficiency
17
Detector Profiles
18
Minimum Source-Detector Distances
19
Coincident Detection(Multiple Emission)
  • R1?1xD1xA
  • R2 ?2xD2xA
  • R12 ?1xD1x ?2xD2xA
  • RR1R2-R12

20
Absorption and Scatter (1)
  • Absorption and scatter occur when radionuclide is
    embedded within some media (tissue for instance).
  • Counting rate is decreased by absorption but may
    be decreased or increased by scattering depending
    on the numbers of the scattering from and into
    the detector.
  • Absorption and scatter are dependent on the ?
    energy, depth within the medium and if the energy
    selective counting is used.

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22
Absorption and Scatter (2)
  • Absorption and scattering decreases with increase
    of the ? energy
  • Absorption may predominate if the radionuclide is
    embedded in greater depth.
  • Scattering is increased initially and reaching a
    maximum and then decreased with the increase of
    energy.

23
Determination of Detection Efficiency
  • Use known calibration source
  • Calculation by definition equation DR/?
  • Take into account the emission frequency if the
    calibration source is differing from the
    radionuclide concerned (see next table).

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26
Problems in the detection and measurement of beta
particles
  • Liquid Scintillation Detectors are generally used
    for short ranged ß particle detection.
  • A survey meter may be used to detect surface
    contamination by ß particles provided it has an
    entrance window sufficiently thin to permit the ß
    particles to enter the sensitive volume of the
    detector

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28
Gas Filled Detectors in ß Assay
  • Sample self absorption (before reaching the
    detector) and backscattering (from sample and
    sample holder) are the problems.
  • Self absorption depends on sample thickness and ß
    energy (strong absorption for low energy and
    thicker samples).
  • Backscattering increases the sample counting rate
    (20-30).

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31
NaI(Tl) For High Energy ß
  • NaI(Tl) detectors can be used to detect higher
    energy ß emitting radionuclides (32P, Emax1.7
    Mev, not 14C, Emax0.156MeV) by counting the
    Bremsstrahlung radiation.
  • Greater activities are required (1000 times more
    than ? emitters) because of the low production
    efficiency of Bremsstrahlung radiation.

32
Deadtime
  • Cause of Deadtime
  • Mathematical Models
  • Window Fraction Effects
  • Deadtime Correction Methods

33
Causes of Deadtime (1)
  • Deadtime is the time required for the counting
    system to process an individual event (it is also
    called pulse resolving time t).
  • Several components (detector, pulse amplifiers,
    pulse high analyzer, scaler and computer
    interface) could contribute to the deadtime and
    the longest component determines the system
    deadtime.

34
Causes of Deadtime (2)
  • The deadtime of NaI(Tl) or semiconductor
    detectors are mainly caused by pulse amplifiers
    (pulse pileup and baseline shift, typical 0.5-5
    µsec)
  • GM tubes are mainly caused by detectors pulse
    overlap (typical 50-200 µsec).
  • Deadtime results in counting losses (overlap loss
    or window shift loss).

35
Mathematical Models
  • Counting systems can be classified as paralyzable
    and non-paralyzable type and most of nuclear
    medicine systems are paralyzable type.
  • A non-paralyzable system is one for which, if an
    event occurs during the deadtime t of a preceding
    event, then the second event is simply ignored.
  • A paralyzable system is one for which each event
    introduces a deadtime t whether or not that event
    actually was counted.

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Nonparalyzable Systems(1)
  • The relationship between observed count rate Ro
    and true count rate Rt for the nonparalyzable
    system is given by

38
Nonparalyzable Systems(2)
  • The observed counting rate Ro has a maximum
    value. For nonparalyzable system, it is given by

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Paralyzable Systems(1)
  • The relationship between observed count rate and
    true count rate for the paralyzable system is
    given by

41
Paralyzable Systems(2)
  • The observed counting rate Ro also has a maximum
    value. For paralyzable system, it is given by

42
Deadtime Losses
  • Deadtime losses is defined as (Rt-Ro) and the
    percentage losses (PL) is given by

43
Window Fraction Effects
  • Deadtime losses depend on total counting
    spectrum.
  • Deadtime per event in the selected window depends
    on the fraction of the window ta t/wf
  • Window fraction effect must be considered in
    comparing deadtime of different systems using
    energy selective counting

44
Deadtime Correction Methods
  • True counting rate can be calculated if we know
    the deadtime and the observed counting rate
    (either use the equation for nonparalyzed system
    directly or use graphic or approximation for
    paralyzed system).
  • Deadtime can be calculated by using the maximum
    observed counting rates
  • Deadtime can also be measured by using two source
    method

45
The Two Source Method
  • Two equal sources and three measurements, R1,
    R12, R2. Equal time should be used in short lived
    radionuclide to avoid decay correction.
  • The dead times are calculated by

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Fixed Rate Pulser Method
  • A fixed rate pulser is connected to the
    preamplifier of the radiation detector.
  • Different input pulse rates (Pt) are generated
    (pulse hight larger than the photo-peak) and the
    observed counting rates (Po) are recorded.
  • Real detector system is then connected to the
    preamplifier and the observed counting rates (Ro)
    are measured. The true counting rate (Rt) is then
    calculated by

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