Radiation Protection Instrumentation Flashcards

1
Q

What is the difference between the quantities; air kerma, H*(10), Hp(10), Hp(3) and Hp(0.07)? Give examples of when these quantities might be measured and possible units.

A
  • Air kerma is the kinetic energy released per unit mass of air due to ionisation. It is a physical quantity and is typically measured with an ionisation chamber in units of J/Kg or Gy.
  • H*(10) is ambient dose equivalent - the operational dose quantity for area monitoring of strongly penetrating radiation. This could be measured with a survey meter in microSv/hr, for example.
  • Hp(10), Hp(3) and Hp(0.07) are the personal dose equivalent operational quantities for whole body dose, dose to the lens of the eye and dose to the skin or extremities, respectively. The numbers represent the appropriate depth within the body. These quantities would be measured with personal dosimetry in mSv.
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2
Q

What are the three types of detectors typically used in radiation protection?

A
  • Gas-filled detectors.
  • Scintillation detectors.
  • Semiconductor (solid state) detectors.
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3
Q

How is detection efficiency different for alpha/beta detectors and gamma/x-ray/neutron detectors?

A
  • Alphas and betas only need to travel a short distance before interaction and, therefore, detection. This means it is likely the detector detects every charged particle entering the active volume and a counting efficiency of 100% is possible.
  • For gamma/x-ray/neutrons, large distances may be travelled before any interaction. This means the efficiency is often less than 100%.
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4
Q

What is the absolute efficiency and intrinsic efficiency of a detector?

A
  • Absolute efficiency = No. of pulses recorded/No. of radiation quanta emitted by source. This, therefore, depends heavily on the setup geometry (e.g. source-to-detector distance) alongside detector and radiation properties.
  • Intrinsic efficiency = No. of pulses recorded/No. of radiation quanta incident on detector. This, therefore, depends on on detector properties (e.g. thickness of detector in direction of incident radiation) more, as well as setup geometry and radiation properties.
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5
Q

What is the difference between total efficiency and peak efficiency?

A
  • Total efficiency: All detected interactions are counted towards the efficiency calculation.
  • Peak efficiency: Only interactions depositing the full energy of the incident radiation are counted towards the efficiency calculation.
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6
Q

What is detector dead time? What is the effect of this?

A
  • The minimum amount of time between two detection events such that they are recorded as two separate pulses. This could be due to the detector or electronics.
  • Due to the random nature of radioactive decay, it is possible that an event may be lost due to this dead time. Corrections, therefore, must be applied for this.
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7
Q

What are paralysable and non-paralysable systems?

A
  • Paralysable: Each detection event occurring during the dead time of the detector will not be recorded as a count but will restart the dead time. Eventually, no events would be recorded at all for high count rates in this type of system.
  • Non-paralysable: Events occurring during the dead time of the detector are lost and have no affect on the behaviour of the detector.
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8
Q

What is the energy resolution of a detector?

A
  • This is the ability of the detector to distinguish between two incident radiations of different energy. This can be determined from a plot of the number of pulses per pulse height vs pulse height using the following equation:
    R = FWHM/H0 where FWHM is the full width half maximum of the resultant peak (equal to 2.35sigma) and H0 is the average pulse height.
  • Therefore, the lower the value of R, the better the energy resolution of the system. More fluctuations from pulse to pulse will correspond to a poorer energy resolution.
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9
Q

What is the typical averaging period for most handheld count-based instruments to ensure uncertainty in the estimated count rate is acceptable?

A

Typically 5 s for lower count rates and 0.5 s for higher count rates. This takes into account the Poisson statistics associated with radiation (i.e. sigma = sqrt(N)).

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10
Q

Explain the regions of operation for gas-filled detectors referencing a pulse height vs bias voltage plot.

A
  • Recombination region: At low bias voltages, some ions created by the incident radiation will recombine before reaching the electrodes and so will not be detected. This effect will become less apparent as bias voltage is increased and pulse height will increase linearly.
  • ion chamber region (after bias voltage is further increased): Recombination will cease and all ions will be collected. This will result in a flat response in which the resultant pulse height is independent of small variations in bias voltage but dependent on the energy of incident radiation.
  • Proportional region: Further increases in bias voltage result in avalanche multiplication with pulse height becoming linearly dependent on bias voltage.
  • Limited proportionality region: This linear proportionality will than begin to change as cascading ionisations begin.
  • Geiger-Muller region: In this region, cascading ionisations become the major effect. The large signals apparent can be useful for radiation counters. Signal is not proportional to the energy of incident radiation.
  • Eventually, continuous discharge will become apparent whereby a large number of cascade avalanches occur in a short period of time. This results in a build up of positive charge near the anode, reducing the electric field and terminating the Geiger discharge.
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11
Q

Briefly describe how an ionisation chamber works. What does an ionisation chamber measure and how is this converted to a dose value?

A
  • Chamber containing air at normal atmospheric pressure.
  • Outer (chamber) and central electrode held a few 100 V potential difference.
  • Incident radiation ionises gas.
  • Resultant ion pairs are collected at electrodes.
  • Resultant current proportional to radiation dose. It also depends on the mass of air irradiated.
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12
Q

What does an ionisation chamber measure and how is this converted to a dose value? How is this conversion applied in practice? What corrections are required for calibrated field instrument measurements?

A
  • Specific charge (C/Kg) is measured. This can be converted to air kerma (J/Kg) by multiplying by the average energy required to create an ion pair (J/C).
  • In practice, air kerma conversions are established in primary standards laboratories using a free air ionisation chamber for which the mass of air is precisely known.
  • Further corrections are applied for beam quality, fraction of the beam lost to Bremsstrahlung, field distortion, air attenuation, recombination, scattered photons etc.
  • This calibration can be applied to a secondary standard which can then be used to calibrate field instruments.
  • Field instruments still have to be corrected for temperature and pressure where absorption efficiency changes depending on these parameters due to the changes in volume of air. The ideal gas laws (P1V1/T1 = P2V2/T2) can be used to determine the correction where it is assumed gas volume is proportional to the current produced.
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13
Q

List some pros and cons of ionisation chambers.

A

Pros:
- Linear response across large dynamic range.
- Variable chamber size for variable sensitivity/spatial resolution.
- Good for standards cross-calibrations.
- Can measure dose rate or accumulated dose.
Cons:
- Electrometers required for readout are limited by leakage current.
- Temperature/pressure corrections required.

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14
Q

Give some examples of uses of ionisation chambers.

A
  • Survey meters.
  • AECs.
  • Beam outputs (e.g. Farmer chamber for RT, Radcal PDC for DR etc.).
  • Dose calibrators.
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15
Q

How does proportional counter work?

A
  • Proportional counters operate in the proportional region, using increased bias voltage when compared to ionisation chambers.
  • The increased bias voltage means the ion pairs created from incident radiation have enough energy to create an avalanche of further ionisations.
  • Each avalanche created is independent of those created from other initial events.
  • They can, therefore, allow for energy discrimination.
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16
Q

Give some examples of uses of proportional counters.

A
  • Large area contamination monitors that can separately count alpha/beta activity.
  • Neutron detectors. Polythene surrounding moderates energetic neutrons to thermal energies. Thermal neutrons interact with proportional counter gas of high neutron interaction cross-section causing ionisations.
  • Low energy gamma peaks can be discriminated via energy discrimination.
  • Detection and spectroscopy of soft x-rays (e.g. x-ray astronomy).
17
Q

What are some pros and cons of proportional counters?

A

Pros:
- Energy discrimination is possible.
- Large area detectors can be constructed.
- Generally good uniformity in detection efficiency.
Cons:
- Not very robust (delicate anode wires, damage to large area windows etc.).
- Counting efficiency low for higher energies.
- Voltage stabilisation required as multiplication factor varies rapidly with small changes in voltage.

18
Q

How do Geiger-Muller counters work?

A
  • The increased bias voltages used results in cascades of avalanche ionisations from the initial event.
  • For a fixed voltage, approximately the same number of avalanches occur resulting in pulses of the same amplitude, regardless of the number of ion pairs that initiated the process.
  • This means no energy discrimination is possible and GM counters are only counting devices.
19
Q

What are the typical properties of the gas used in a Geiger-Muller counter?

A
  • Typically an inert noble gas.
  • Quenching required to prevent excessive pulsing. Quenching neutralises leftover positive ions post-discharge to prevent them drifting to the cathode, liberating further electrons and causing further cascade ionisation events unrelated to the radiation event.
20
Q

What does the effective efficiency of a Geiger-Muller counter depend on? How does this relate to the energy response? How is energy compensation performed?

A
  • Depends on the probability of the incident particle penetrating the window without absorption or backscatter.
  • Probability of interaction is low.
  • Medium energy photons are most likely to interact with the wall material. This results in a non-uniform energy response.
  • Energy compensation for different radiation types can be performed by covering the tube with an external layer of lead and/or tin to preferentially absorb lower energy photons.
21
Q

Give some examples of use of Geiger-Muller counters.

A
  • Low dose contamination monitoring.
  • Energy compensated low dose rate monitors (e.g. RamGene monitors). These can only be used at certain photon energy ranges due to fall off in sensitivity below this range. Above this range, low energy scatter radiation will affect measurements.
22
Q

What are some pros and cons of Geiger-Muller counters?

A

Pros:
- Robust construction.
- Increased sensitivity over ionisation chamber.
- Can detect all radiation types with appropriate entrance windows.
- Cheap.
Cons:
- Large dead time compared to other detectors to allow positive charges to disperse and the electric field to return to the original value. This means they are limited to low count rate uses and can not be used for high dose rates.
- Energy discrimination not possible where the pulse is always the same, regardless of the energy of incident radiation.

23
Q

How does a scintillator detector work? What makes a good scintillation material?

A
  • Radiation incident on a scintillator material results in ionisation. Fluorescence (prompt emission of visible photons) occurs when electrons relax into lower energy levels.
  • Visible light photons are detected via a coupled photomultiplier tube, CCD or photodiode.

Detector material properties include:
- High scintillation efficiency.
- Light yield proportional to deposited energy.
- Material transparent to the light it produces.
- Fast luminescence after after interaction with incident radiation.
- Large enough for detector.
- Good coupling to photomultiplier tube (i.e. refractive index similar to glass), CCD or photodiode.
- Matched to the type of radiation. Gamma rays require high Z material (e.g. Tl doped NaI). This results in good light output and linearity but slow response time. Beta requires an organic material with lower Z. This results in a faster response time but lower light yield.

24
Q

How does the photomultiplier aspect of a scintillation detector work? What information do the resultant pulses provide?

A
  • Light photons from scintillator material incident on photocathode which converts photons to electrons.
  • Focussing electrodes focus these electrons onto a set of successive dynodes which multiplies the number of electrons.
  • The pulse carries information regarding the energy of incident radiation.
  • The number of pulses carried information regarding the intensity of the radiation.
25
Q

What are some typical uses of scintillation detectors?

A
  • Survey dose rate meters.
  • Photon and beta contamination monitors.
  • Gamma scintillation spectroscopy.
26
Q

What are the pros and cons associated with scintillation detectors?

A

Pros:
- Energy discrimination is possible.
- High detection efficiency.
Cons:
- Light leakage issues means robust casing is required. This can reduce sensitivity to lower energy alphas and betas. A thin energy window is required to compensate and this could potentially be easily damaged.
- Energy resolution is relatively poor.

27
Q

How does a semiconductor solid state detector work?

A
  • An electric field is applied across a semiconductor material (e.g. silicon, germanium etc.).
  • Incident radiation frees bound electrons in the valence band creating holes in the process.
  • Electrons and holes move in different directions as a result of the applied electric field and a pulse is detected at the electrodes.
  • The material is typically doped and reverse-biased to create a P-N junction separated by a depletion layer. This improves speed and efficiency of detection due to increased potential difference.
  • The energy required to produce electron-hole pairs is much lower than that associated with gas ionisation. This means energy resolution is better.
28
Q

What are some typical uses of semiconductor solid state detectors?

A
  • DR QA.
  • Electronic personal dosimetry.
29
Q

What are some pros and cons of semiconductor solid state detectors?

A

Pros:
- Excellent energy resolution.
- Compact size.
- Fast timing characteristics.
- Effective thickness can be varied to match application.
Cons:
- Limitation to small sizes.
- Relatively high susceptibility to radiation induced damage.
- Non-linear energy response.

30
Q

What are the requirements for monitoring equipment in IRR17?

A
  • Throughly examined and tested before first use.
  • Properly maintained so that it reminds fit for purpose.
  • Adequately tested and examined at appropriate intervals (at least once a year).
  • Testing performed by a ‘Qualified Person’
  • More frequent checks should be performed within the department.
  • Pre-use checks (e.g. battery check, background reading, general physical condition).
  • Suitable records of testing should be kept.
31
Q

Which guidance document covers the calibration of radiation protection monitors?

A

National Physics Laboratory (NPL) Good Practice Guidance No.14: The Examination, Testing and Calibration of Portable Radiation Protection Instruments.

32
Q

What are some routine non-radiation checks performed on both dose rate and contamination monitors?

A
  • Visual inspection of physical condition.
  • Battery check.
  • High voltage check.
  • Background check.
  • Light leakage.
  • Audio speaker function check.
33
Q

What are some routine radiation checks performed on contamination monitors?

A
  • Response to high dose rates (full scale deflection apparent? Alarm function triggered?).
  • Linearity: Instrument response to point sources covering each range/decade of the detector. Agreement should be to within 30% of reference data. Should also agree to within 30% of the mean of all linearity responses.
  • Responses to large area sources. Response should be to within 30% of reference data.
  • Uniformity of response is checked for large area probes. No more than 25% of the total detector area should have a response that is less than 35% of the mean response.
34
Q

What are some routine radiation checks performed on dose rate meters?

A
  • Response to high dose rates (full scale deflection? Alarm set?).
  • Linearity: Instrument response to point sources covering each range/decade of the detector. Agreement should be to within 30% of reference data. Should also agree to within 30% of the mean of all linearity responses.
  • Energy dependence: Whether the instruments responds satisfactorily at low energies is checked with a low energy source. Response should be to within 30% of reference data.
  • Directional dependence (only at baseline): Low energy source used (test more sensitive) and instrument rotate 90 degrees away from source to check response. Response should be to within 30% of reference data.
35
Q

What factors may come into instrument selection?

A
  • Need to ensure instrument is appropriate to the nature of the radiation being detected (i.e. consider radiation type, energy response, sensitivity, response time, accuracy etc.).