Geiger counter

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Geiger–Müller counter
A "two-piece" bench type Geiger–Müller counter with end-window detector.
Other names Geiger counter
Uses Particle detector
Inventor

Hans Geiger

Walther Muller
Related items Geiger–Müller tube

The Geiger–Müller counter, also called a Geiger counter, is an instrument used for measuring ionizing radiation.

It detects radiation such as alpha particles, beta particles and gamma rays using the ionization produced in a Geiger–Müller tube, which gives its name to the instrument. [1] In wide and prominent use as a hand-held radiation survey instrument, it is perhaps one of the world's best-known radiation instruments.

The original detection principle was discovered in 1908, but it was not until the development of the Geiger-Müller tube in 1928 that the Geiger-Müller counter became a popular instrument for use in such as radiation dosimetry, radiological protection, experimental physics and the nuclear industry. This was mainly due to its robust sensing element and relatively low cost, however there are limitations in measuring high radiation rates and in measuring the energy of incident radiation.[2]

Principle of operation

Schematic of a Geiger counter using an "end window" tube for low penetration radiation.
Main article: Geiger-Müller tube

The Geiger counter consists of two main elements; the Geiger-Müller tube which detects the radiation, and the processing and display electronics. The Geiger-Müller tube is filled with an inert gas such as helium, neon, or argon at low pressure, which briefly conducts electrical charge when a particle or photon of incident radiation makes the gas conductive by ionization. The ionization current is greatly amplified within the tube by the Townsend avalanche effect to produce an easily measured detection pulse. This makes the G-M counter relatively cheap to manufacture, as the subsequent electronic processing is greatly simplified.[2]

The article on the Geiger-Muller tube has a more detailed description of the fundamental ionisation mechanism.

Readout

There are fundamentally two types of radiation readout; counts or radiation dose. The counts display is the simplest and is the number of ionizing events displayed either as a count rate, commonly "counts per second", or as a total over a set time period (an integrated total). The counts readout is normally used when alpha or beta particles are being detected. More complex to achieve is a display of radiation dose rate, displayed in a unit such as the sievert which is normally used for measuring gamma or X-ray dose rates. However a G-M tube can detect the presence of radiation, but not its energy which also influences the radiation's ionising effect. Consequently, dose rate measurement requires the use of an energy compensated G-M tube, so that the dose displayed relates to the counts detected.[2] The electronics will apply known factors to make this conversion, which is specific to each instrument and is determined by design and calibration.

The readout can be analog or digital, and increasingly, modern instruments are offering serial communications with a host computer or network.

There is usually an option to produce audible clicks representing the number of ionization events detected. This is the distinctive sound normally associated with hand held or portable Geiger counters. The purpose of this is to allow the user to concentrate on manipulation of the instrument whilst retaining auditory feedback on the radiation rate.

The electronics also generates the relatively high voltage, typically 400–600 volts, that has to be applied to the Geiger-Müller tube to enable its operation.

Limitations

There are two main limitations of the Geiger counter. Because the output pulse from a Geiger-Müller tube is always the same magnitude regardless of the energy of the incident radiation, the tube cannot differentiate between radiation types.[2] A further limitation is the inability to measure high radiation rates due to the "dead time" of the tube. This is an insensitive period after each ionization of the gas during which any further incident radiation will not result in a count, and the indicated rate is therefore lower than actual. Typically the dead time will reduce indicated count rates above about 104 to 105 counts per second depending on the characteristic of the tube being used.[2] Whilst some counters have circuitry which can compensate for this, for accurate measurements ion chamber instruments are preferred for high radiation rates.

Types and applications

G-M counter with pancake type probe
Laboratory use of a G-M counter with end window probe to measure beta radiation from a radioactive source

The application and use of a Geiger counter is dictated entirely by the design of the tube, of which there are a great many, but they can be generally categorised as "end-window", or windowless "thin-walled" or "thick-walled", and sometimes hybrids of these types.

Particle detection

The first historical uses of the Geiger principle were for the detection of alpha and beta particles, and the instrument is still used for this purpose today. For alpha particles and low energy beta particles the "end-window" type of G-M tube has to be used as these particles have a limited range even in free air, and are easily stopped by a solid material. Therefore the tube requires a window which is thin enough to allow as many as possible of these particles through to the fill gas. The window is usually made of mica with a density of about 1.5 - 2.0 mg/cm2. [1]

Alpha particles have the shortest range, and to detect these the window should ideally be within 10mm of the radiation source due to alpha particle attenuation in free air.[1] However, the G-M tube produces a pulse output which is the same magnitude for all detected radiation, so a Geiger counter with an end window tube cannot distinguish between alpha and beta particles.[2] A skilled operator can use distance to differentiate alpha and high energy beta, but with the detector in close contact with the radiation source the types are indistinguishable. The "pancake" Geiger-Muller detector is a variant of the end window probe, but designed with a larger detection area to make checking quicker. However the pressure of the atmosphere against the low pressure of the fill gas limits the window size due to the limited strength of the window membrane.

High energy beta particles are can also be detected by a thin-walled "windowless" G-M tube, which has no end window. Although the tube walls have a greater stopping power than a thin end window, they still allow these more energetic particles to reach the fill gas.[1]

End-window G-M detectors are still used as a general purpose portable Radioactive contamination measurement and detection instrument, owing to their relatively low cost, robustness and their relatively high detection efficiency; particularly with high energy beta particles.[2] However for discrimination between alpha and beta particles or provision of particle energy information, scintillation counters or proportional counters should be used.[3] Those instrument types are manufactured with much larger detector areas, which means that checking for surface contamination is quicker than with a G-M instrument.

Gamma and X-ray detection

Geiger counters are widely used to detect gamma radiation, and for this the windowless tube is used. However, efficiency is generally low due to the poor interaction of gamma rays compared with alpha and beta particles. For instance, a chrome steel G-M tube is only about 1% efficient over a wide range of energies.[1]

The article on the Geiger-Muller tube carries a more detailed account of the techniques used to detect photon radiation. For high energy gamma it largely relies on interaction of the photon radiation with the tube wall material, usually 1–2 mm of chrome steel on a "thick-walled" tube, to produce electrons within the wall which can enter and ionize the fill gas.[2] This is necessary as the low pressure gas in the tube has little interaction with high energy gamma photons. However, for low energy photons there is greater gas interaction and the direct gas ionisation effect increases. With decreasing energy the wall effect gives way to a combination of wall effect and direct ionisation, until direct gas ionisation dominates. Due to the variance in response to different photon energies, thick walled steel tubes employ what is known as "energy compensation" which attempts to compensate for these variations over a large energy range.[1]

Low energy photon radiation such as low energy X rays or gamma rays interacts better with the fill gas. Consequently a typical design for low energy photon detection for these is a long tube with a thin wall or with an end window. The tube has a larger gas volume than a steel walled tube to give an increased chance of particle interaction.[1]

Neutron detection

Geiger tube filled with BF3 for detection of thermal neutrons

A variation of the Geiger tube is used to measure neutrons, where the gas used is boron trifluoride or Helium 3 and a plastic moderator is used to slow the neutrons. This creates an alpha particle inside the detector and thus neutrons can be counted.

Gamma measurement—personnel protection and process control

The term "Geiger counter" is commonly used to mean a hand-held survey type meter, however the Geiger principle is in wide use in installed "area gamma" alarms for personnel protection, and in process measurement and interlock applications. A Geiger tube is still the sensing device, but the processing electronics will have a higher degree of sophistication and reliability than that used in a hand held survey meter.

Physical design

Pancake G-M tube used for alpha and beta detection; the delicate mica window is usually protected by a mesh when fitted in an instrument.

For hand-held units there are two fundamental physical configurations: the "integral" unit with both detector and electronics in the same unit, and the "two-piece" design which has a separate detector probe and an electronics module connected by a short cable.

The integral unit allows single-handed operation, so the operator can use the other hand for personal security in challenging monitoring positions, but the two piece design allows easier manipulation of the detector, and is commonly used for alpha and beta surface contamination monitoring where careful manipulation of the probe is required or the weight of the electronics module would make operation unwieldy. A number of different sized detectors are available to suit particular situations, such as placing the probe in small apertures or confined spaces.

Gamma and X-Ray detectors generally use an "integral" design so the Geiger–Müller tube is conveniently within the electronics enclosure. This can easily be achieved because the casing usually has little attentuation, and is employed in ambient gamma measurements where distance from the source of radiation is not a significant factor. However, to facilitate more localised measurements such as "surface dose", the position of the tube in the enclosure is sometimes indicated by targets on the enclosure so an accurate measurement can be made with the tube at the correct orientation and a known distance from the surface.

There is a particular type of gamma instrument known as a "hot spot" detector which has the detector tube on the end of a long pole or flexible conduit. These are used to measure high radiation gamma locations whilst protecting the operator by means of distance shielding.

Particle detection of alpha and beta can used in both integral and two-piece designs. A pancake probe (for alpha/beta) is generally used to increase the area of detection in two-piece instruments whilst being relatively light weight. In integral instruments using an end window tube there is a window in the body of the casing to prevent shielding of particles. There are also hybrid instruments which have a separate probe for particle detection and a gamma detection tube within the electronics module. The detectors are switchable by the operator, depending the radiation type that is being measured.

Guidance on application use

In the United Kingdom the HSE has issued a user guidance note on selecting the best portable instrument type for the radiation measurement application concerned [1].[3] This covers all radiation protection instrument technologies and is a useful comparative guide to the use of G-M detectors. The guide does not recommend the G-M detector for mixed alpha and beta contamination detection, and they are only recommended as "satisfactory" for beta-only contamination. However for gamma and low-voltage X-rays they are recommended as the best instrument type.

History

An early alpha particle counter designed by Rutherford and Geiger.
Early Geiger-Muller tube made in 1932 by Hans Geiger for laboratory use

In 1908 Hans Geiger, under the supervision of Ernest Rutherford at the Victoria University of Manchester (now the University of Manchester), developed an experimental technique for detecting alpha particles that would later be used in the Geiger-Müller tube.[4] This early counter was only capable of detecting alpha particles and was part of a larger experimental apparatus. The fundamental ionization mechanism used was discovered by John Sealy Townsend by his work between 1897 and 1901,[5] and is known as the Townsend discharge, which is the ionization of molecules by ion impact.

It was not until 1928 that Geiger and Walther Müller (a PhD student of Geiger) developed the sealed Geiger-Müller tube which developed the basic ionisation principles previously used experimentally. This was relatively small and rugged, and could detect more types of ionizing radiation.[6] Now a practical radiation instrument could be produced relatively cheaply, and so the Geiger-Muller counter was born. As the tube output required little electronic processing, a distinct advantage in the thermionic valve era due to minimal valve count and low power consumption, the instrument achieved great popularity as a portable radiation detector.

Modern versions of the Geiger counter use the halogen tube invented in 1947 by Sidney H. Liebson.[7] It superseded the earlier Geiger tube because of its much longer life and lower operating voltage, typically 400-600 volts.[8]

Gallery

See also

References

  1. ^ a b c d e f g ’’Geiger Muller Tubes; issue 1’’ published by Centronics Ltd, UK.
  2. ^ a b c d e f g h Glenn F Knoll. Radiation Detection and Measurement, third edition 2000. John Wiley and sons, ISBN 0-471-07338-5
  3. ^ a b Selection, use and maintenance of portable monitoring instruments - Ionising Radiation Protection Series No 7, issue 10/01. Pub by United Kingdom Health and Safety Executive.
  4. ^ E. Rutherford and H. Geiger (1908) "An electrical method of counting the number of α particles from radioactive substances," Proceedings of the Royal Society (London), Series A, vol. 81, no. 546, pages 141–161.
  5. ^ John S. Townsend (1901) "The conductivity produced in gases by the motion of negatively charged ions," Philosophical Magazine, series 6, 1 (2) : 198-227.
  6. ^ See:
    • H. Geiger and W. Müller (1928), "Elektronenzählrohr zur Messung schwächster Aktivitäten" (Electron counting tube for the measurement of the weakest radioactivities), Die Naturwissenschaften (The Sciences), vol. 16, no. 31, pages 617–618.
    • Geiger, H. and Müller, W. (1928) "Das Elektronenzählrohr" (The electron counting tube), Physikalische Zeitschrift, 29: 839-841.
    • Geiger, H. and Müller, W. (1929) "Technische Bemerkungen zum Elektronenzählrohr" (Technical notes on the electron counting tube), Physikalische Zeitschrift, 30: 489-493.
    • Geiger, H. and Müller, W. (1929) "Demonstration des Elektronenzählrohrs" (Demonstration of the electron counting tube), Physikalische Zeitschrift, 30: 523 ff.
  7. ^ S. H. Liebson (1947) "The discharge mechanism of self-quenching Geiger-Mueller counters," Physical Review, vol. 72, no. 7, pages 602–608.
  8. ^ History of Portable Radiation Detection Instrumentation from the period 1920–60

External links

Media related to Geiger counters at Wikimedia Commons