Silicon detectors with diameters of up to several centimetres and thicknesses of several hundred micrometres are common choices for heavy charged particle detectors. They are fabricated from extremely pure or highly resistive silicon that is mildly n- or p-type owing to residual dopants. (Doping is the process in which an impurity, called a dopant, is added to a semiconductor to enhance its conductivity. If excess positive holes are formed as a result of the doping, the semiconductor is a p-type; if excess free electrons are formed, it is an n-type semiconductor.) A thin layer of the oppositely doped silicon is created on one surface, forming a rectifying junction—i.e., one that allows current to flow freely in only one direction. If voltage is now applied to reverse-bias this diode so that the free electrons and positive holes flow away from the junction, a depletion region is formed in the vicinity of the junction. In the depletion region, an electric field exists that quickly sweeps out electron-hole pairs that may be thermally generated and reduces the equilibrium concentration of the charge carriers to exceedingly low levels. Under these circumstances the additional electron-hole pairs suddenly created by the energy deposited by a charged particle now become detectable as a pulse of current produced from the detector. Raising the applied voltage increases the thickness of the depletion layer, and fully depleted configurations are commercially available in which the depletion region extends from the front to back surfaces of the silicon wafer. The entire volume of silicon then becomes the active volume of the detector. Silicon diode detectors with thicknesses of less than a millimetre are generally small enough in volume so that the thermally generated carriers can be tolerated, allowing operation of these detectors at room temperature.

These simple silicon diode detectors are presently limited to depletion depths of about one millimetre or less. In order to create thicker detectors, a process known as lithium-ion drifting can be employed. This process produces a compensated material in which electron donors and acceptors are perfectly balanced and that behaves electrically much like a pure semiconductor. By fabricating n- and p-type contacts onto the opposite surface of a lithium-drifted material and applying an external voltage, depletion thicknesses of many millimetres can be formed. These relatively thick lithium-drifted silicon detectors are widely used for X-ray spectroscopy and for the measurement of fast-electron energies. Operationally, they are normally cooled to the temperature of liquid nitrogen to minimize the number of thermally generated carriers that are spontaneously produced in the thick active volume so as to control the associated leakage current and consequent loss of energy resolution.

Germanium detectors

Semiconductor detectors also can be used in gamma-ray spectroscopy. In this case, however, it is advantageous to choose germanium rather than silicon as the detector material. With an atomic number of 32, germanium has a much higher photoelectric cross section than silicon (atomic number, Z, of 14), as the probability of photoelectron absorption varies approximately as Z4.5. Therefore, it is far more probable for an incident gamma ray to lose all its energy in germanium than in silicon, and the intrinsic peak efficiency for germanium will be many times larger. In gamma-ray spectroscopy, there is an advantage in using detectors with a large active volume. The depletion region in germanium can be made several centimetres thick if ultrapure material is used. Advances in germanium purification processes in the 1970s have led to the commercial availability of material in which the residual impurity concentration is about one part in 1012.

The most common type of germanium gamma-ray spectrometer consists of a high-purity (mildly p-type) crystal fitted with electrodes in a coaxial configuration. Normal sizes correspond to germanium volumes of several hundred cubic centimetres. Because of their excellent energy resolution of a few tenths of a percent, germanium coaxial detectors have become the workhorse of modern-day high-resolution gamma-ray spectroscopy. The band gap in germanium is smaller than that in silicon, so thermally generated charge carriers are even more of a potential problem. As a result, virtually all germanium detectors, even those with relatively small volume, are cooled to liquid-nitrogen temperature during their use. Typically, the germanium crystal is sealed inside a vacuum enclosure, or cryostat, that provides thermal contact with a storage dewar of liquid nitrogen. Mechanical refrigerators are also available to cool the detector for use in remote locations where a supply of liquid nitrogen may not be available.

Although semiconductor detectors can be operated in current mode, the vast majority of applications are best served by operating the device in pulse mode to take advantage of its excellent energy resolution. The time required to collect the electrons and holes formed along a particle track is typically tens to hundreds of nanoseconds, depending on detector thickness. The rise time of the output pulse is therefore of the same order, and relatively precise timing measurements are possible, especially for thin detectors.

Scintillation and Cherenkov detectors

One of the overworked images of radiation in popular perception is the idea that radioactive materials glow, emitting some form of eerie light. Most materials when irradiated do not emit light; however, low-intensity visible and ultraviolet light can be detected from some transparent materials owing to the energy deposited by interacting charged particles. The intensity of this light is far too small to be seen with the naked eye under ordinary circumstances, and visible glowing requires radiation fields of extraordinary intensity. One example is the blue luminescence that can be seen in the water surrounding the core of some types of research reactors. This light originates from the Cherenkov radiations (see below) from secondary electrons produced by the extremely intense gamma-ray flux emerging from the reactor core.

Scintillators

In certain types of transparent materials, the energy deposited by an energetic particle can create excited atomic or molecular states that quickly decay through the emission of visible or ultraviolet light, a process sometimes called prompt fluorescence. Such materials are known as scintillators and are commonly exploited in scintillation detectors. The amount of light generated from a single charged particle of a few MeV kinetic energy is very weak and cannot be seen with the unaided eye. However, some early historic experiments by the British physicist Ernest Rutherford on alpha-particle scattering were carried out by manually counting scintillation flashes from individual alpha particles interacting in a zinc sulfide screen and viewed through a microscope. Modern scintillation detectors eliminate the need for manual counting by converting the light into an electrical pulse in a photomultiplier tube or photodiode.

There are four distinct steps involved in the production of a pulse of charge due to a single energetic charged particle:

1. The particle slows down and stops in the scintillator, leaving a trail of excited atomic or molecular species along its track. The particle may be incident on the detector from an external source, or it may be generated internally by the interaction of uncharged quanta such as gamma rays or neutrons. Typical excited states require only a few electron volts for their excitation; thus many thousands are created along a typical charged particle track.

2. Some of these excited species return to their ground state in a process that involves the emission of energy in the form of a photon of visible or ultraviolet light. These scintillation photons are emitted in all directions. The total energy represented by this light (given as the number of photons multiplied by the average photon energy) is a small fraction of the original particle energy deposited in the scintillator. This fraction is given the name scintillation efficiency and ranges from about 3 to 15 percent for common scintillation materials. The photon energy (or the wavelength of the light) is distributed over an emission spectrum that is characteristic of the particular scintillation material.

The excited species have a characteristic mean lifetime, and their population decays exponentially. The decay time determines the rate at which the light is emitted following the excitation and is also characteristic of the particular scintillation material. Decay times range from less than one nanosecond to several microseconds and generally represent the slowest process in the several steps involved in generating a pulse from the detector. There is often a preference for collecting the light quickly to form a fast-rising output signal pulse, and short decay times are therefore highly desirable in some applications.

3. Some fraction of the light leaves the scintillator through an exit window provided on one of its surfaces. The remaining surfaces of the scintillator are provided with an optically reflecting coating so that the light that is originally directed away from the exit window has a high probability of being reflected from the surfaces and collected. As much as 90 percent of the light can be collected under favourable conditions.

4. A fraction of the emerging light photons are converted to charge in a light sensor normally mounted in optical contact with the exit window. This fraction is known as the quantum efficiency of the light sensor. In a silicon photodiode, as many as 80 to 90 percent of the light photons are converted to electron-hole pairs, but in a photomultiplier tube, only about 25 percent of the photons are converted to photoelectrons at the wavelength of maximum response of its photocathode (see below).

The net result of this sequence of steps, each with its own inefficiency, is the creation of a relatively limited number of charge carriers in the light sensor. A typical pulse will correspond to at most a few thousand charge carriers. This figure is a small fraction of the number of electron-hole pairs that would be produced directly in a semiconductor detector by the same energy deposition. One consequence is that the energy resolution of scintillators is rather poor owing to the statistical fluctuations in the number of carriers actually obtained. For example, the best energy resolution from a scintillator for 0.662 MeV gamma rays (a common standard) is about 5 to 6 percent. By comparison, the energy resolution for the same gamma-ray energy in a germanium detector may be about 0.2 percent. In many applications, the disadvantage of poor energy resolution is offset by other favourable properties, for example, high gamma-ray detection efficiency.

There are many characteristics that are desirable in a scintillator, including high scintillation efficiency, short decay time, linear dependence of the amount of light generated on deposited energy, good optical quality, and availability in large sizes at modest cost. No known material meets all these criteria, and therefore many different materials are in common use, each with attributes that are best suited for certain applications. These materials are commonly classified into two broad categories: inorganic and organic scintillators.

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Inorganic scintillators

Most inorganic scintillators consist of transparent single crystals, whose dimensions range from a few millimetres to many centimetres. Some inorganics, such as silver-activated zinc sulfide, are good scintillators but cannot be grown in the form of optical-quality large crystals. As a result, their use is limited to thin polycrystalline layers known as phosphor screens.

The inorganic materials that produce the highest light output unfortunately have relatively long decay times. The most common inorganic scintillator is sodium iodide activated with a trace amount of thallium [NaI(Tl)], which has an unusually large light yield corresponding to a scintillation efficiency of about 13 percent. Its decay time is 0.23 microsecond, acceptable for many applications but uncomfortably long when extremely high counting rates or fast timing measurements are involved. The emission spectrum of NaI(Tl) is peaked at a wavelength corresponding to the blue region of the electromagnetic spectrum and is well matched to the spectral response of photomultiplier tubes. Thallium-activated cesium iodide [CsI(Tl)] also produces excellent light yield but has two relatively long decay components with decay times of 0.68 and 3.3 microseconds. Its emission spectrum is shifted toward the longer-wavelength end of the visible spectrum and is a better match to the spectral response of photodiodes. Both NaI(Tl) and CsI(Tl) have iodine, with an atomic number of 53, as a major constituent. Therefore the photoelectric cross section in these materials is large enough to make them attractive in gamma-ray spectroscopy. They are available economically in large sizes so that the corresponding gamma-ray intrinsic peak efficiency can be many times greater than that for the largest available germanium detector. Other inorganic scintillation materials are listed in the table. Some recently developed materials have much shorter decay times but, unfortunately, also lower light yields. These materials are useful for timing measurements but will have poorer energy resolution compared with the brighter materials.

Some properties of inorganic scintillators
*Using an ultraviolet-sensitive photomultiplier tube.
**For alpha particles.
***Properties vary with exact formulation.
Source: Adapted from G.F. Knoll, Radiation Detection and Measurement, 2nd ed., copyright © 1989 by John Wiley & Sons, Inc. Reprinted by permission of John Wiley & Sons, Inc.
material specific gravity wavelength of maximum emission (nm) principal decay constant (μs) total light yield (photons/
MeV)
relative gamma-ray pulse height with Bialkali photomultiplier tube
NaI(T1) 3.67 415 0.23 38,000 1.00
CsI(T1) 4.51 560 0.68 65,000 0.49
CsI(Na) 4.51 420 0.63 39,000 1.11
LiI(Eu) 4.08 470 1.4 11,000 0.23
BGO 7.13 505 0.30    8,200 0.13
BaF2
slow component
4.89 310 0.62 10,000 0.13
BaF2
fast component
4.89 220 0.0006 0.03*
ZnS(Ag) (polycrystalline) 4.09 450 0.2 1.30**
CaF2(Eu) 3.19 435 0.9 24,000 0.78
CsF 4.11 390 0.004 0.05
Li glass*** 2.5 395 0.075 0.10
For comparison, a typical organic (plastic) scintillator:
NE 102A 1.03 423 0.002 10,000 0.25

Organic scintillators

A number of organic molecules with a so-called π-orbital electron structure exhibit prompt fluorescence following their excitation by the energy deposited by an ionizing particle. The basic mechanism of light emission does not depend on the physical state of the molecule; consequently, organic scintillators take many different forms. The earliest were pure crystals of anthracene or stilbene. More recently, organics are used primarily in the form of liquid solutions of an organic fluor (fluorescent molecule) in a solvent such as toluene, or as a plastic, in which the fluor is dissolved in a monomer that is subsequently polymerized. Frequently, a third component is added to liquid or plastic scintillators to act as a wave shifter, which absorbs the primary light from the organic fluor and re-radiates the energy at a longer wavelength more suitable for matching the response of photomultiplier tubes or photodiodes. Plastic scintillators are commercially available in sheets or cylinders with dimensions of several centimetres or as small-diameter scintillating fibres.

One of the most useful attributes of organic scintillators is their fast decay time. Many commercially available liquids or plastics have decay times of two to three nanoseconds, allowing their use in precise timing measurements. Organics tend to show a somewhat nonlinear yield of light as the deposited energy increases, and the light yield per unit energy deposited is significantly higher for low dE/dx particles such as electrons than for high dE/dx heavy charged particles. Even for electrons, however, the light yield is two to three times smaller than that of the best inorganic materials.

Because liquids and plastics can be made into detectors of flexible size and shape, they find many applications in the direct detection of charged particle radiations. They are seldom used to detect gamma rays because the low average atomic number of these materials inhibits the full energy absorption needed for spectroscopy. The average atomic number is not greatly different from that of tissue, however, and plastic scintillators have consequently found some useful applications in the measurement of gamma-ray doses. A unique application of liquid scintillators is in the counting of radioisotopes that emit low-energy beta particles, such as hydrogen-3 (3H) or carbon-14 (14C). As these low-energy beta particles have rather short ranges, they can be easily absorbed before reaching the active volume of a detector. This attenuation problem is completely avoided if the sample is dissolved directly in the liquid scintillator. In this case, the beta particles find themselves in the scintillator immediately after being emitted.

Cherenkov detectors

Cherenkov light is a consequence of the motion of a charged particle with a speed that is greater than the speed of light in the same medium. No particle can exceed the speed of light in a vacuum (c), but in materials with an index of refraction represented by n, the particle velocity v will be greater than the velocity of light if v > c/n. For materials with an index of refraction in the common range between 1.3 and 1.8, this velocity requirement corresponds to a minimum kinetic energy of many hundreds of MeV for heavy charged particles. Fast electrons with relatively small kinetic energy can reach this minimum velocity, however, and the application of the Cherenkov process to radiations with energy below 20 MeV is restricted to primary or secondary fast electrons.

Cherenkov light is emitted only during the time in which the particle is slowing down and therefore has very fast time characteristics. In contrast with the isotropically emitted scintillation light, Cherenkov light is emitted along the surface of a forward-directed cone centred on the particle velocity vector. The wavelength of the light is preferentially shifted toward the short-wavelength (blue) end of the spectrum. The total intensity of the Cherenkov light is much weaker than the light emitted from equivalent energy loss in a good scintillator and may be only a few hundred photons or less for a 1-MeV electron. Cherenkov detectors are normally used with the same type of light sensors employed in scintillation detectors.