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textbook:nrctextbook:chapter10 [2025-01-22 18:31] Merja Herzig |
textbook:nrctextbook:chapter10 [2025-04-22 14:52] (current) Merja Herzig |
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| - | Photons and particles emitted in radioactive decay ionize gas molecules which phenomenon is utilized in detection and measurement of radiation. In detectors based on the gas ionization, the ionizable gas is inside a metal chamber, which has typically a cylinder shape and is called tube. A voltage is applied to the tube so that the metal wall acts as cathode and a metal wire in the middle of the tube as anode (Figure X.1). | + | Photons and particles emitted in [[textbook: |
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| Figure X.1. Gas ionization detector | Figure X.1. Gas ionization detector | ||
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| - | ions. Due to electric field applied between the electrodes these argon cations transfer towards the cathode, the tube wall, while the electrons transfer towards the anode, the metal wire in the middle of the tube. From the anode wire the electrons are transported through an external circuit to the tube wall where they neutralize Ar< | + | modes of gas ionization detectors ([[# |
| - | circuit are registered as an electric pulse representing an individual radiation absorption event. Thus the number of electric pulses corresponds to the number of radiation absorptions in the tube which in turn corresponds to the number particles or photons hitting the tube, i.e. the number of pulses corresponds to the activity of the source detected. As will be explained below the height of a pulse corresponds to the energy of a particle or a photon being absorbed in the tube in the case of two | + | |
| - | modes of gas ionization detectors ([[# | + | |
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| Figure X.2. Operation ranges of three gas ionization detectors as a function of high voltage applied across the tube (http:// | Figure X.2. Operation ranges of three gas ionization detectors as a function of high voltage applied across the tube (http:// | ||
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| ===== 10.1. Ionization chamber ===== | ===== 10.1. Ionization chamber ===== | ||
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| - | In the low voltage region, below about 50 V in Figure X.2, the velocities of the electrons and the Ar< | + | In the low voltage region, below about 50 V in Figure X.2, the velocities of the [[textbook: |
| - | ionization chambers are very seldom used for activity measurements. | + | |
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| ===== 10.2. Proportional counter ===== | ===== 10.2. Proportional counter ===== | ||
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| - | As the voltage is further increased from ionization chamber operation range the electrons have such a high energy that they cause additional, secondary ionization. In this range (III) the height of the electric pulse is dependent on the voltage applied. A gas ionization detector working in this range is called proportional counter since the height of the electric pulse, at constant voltage, is proportional to the energy of the photon or particle losing its energy in the filling gas by ionizations. This is | + | As the voltage is further increased from ionization chamber operation range the electrons have such a high energy that they cause additional, |
| - | because the amplification of the electrons due to secondary ionizations is constant providing that the voltage remains the same. Thus, as in case of ionization chamber the proportional counter can be used in nuclear spectrometry, | + | because the amplification of the electrons due to secondary ionizations is constant providing that the voltage remains the same. Thus, as in case of [[textbook: |
| voltage sources. The advantage of proportional counter compared to ionization chamber is that the observed pulse is much higher and thus easier to detect. | voltage sources. The advantage of proportional counter compared to ionization chamber is that the observed pulse is much higher and thus easier to detect. | ||
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| ===== 10.3. Geiger-Műller counter ===== | ===== 10.3. Geiger-Műller counter ===== | ||
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| - | As the voltage is further increased from the proportional counter area all individual particles or photons cause complete ionization of the filling gas (area IV). This means that the observed electric pulses have the same heigth and are thus independent of the energy of the particle or photon losing its energy in the tube. Thus Geiger-Műller counter cannot be used in nuclear spectrometry but only in pulse counting, i.e. determination of activities or radiation intensities. The amplification of electrons in a Geiger-Műller tube is in the range 10< | + | As the voltage is further increased from the proportional counter area all individual particles or photons cause complete |
| - | increased from the Geiger-Műller voltage range there will be a continuous electric discharge (area V) which can destroy the tube rather quickly. | + | |
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| - | In addition to argon (or neon) the filling gas in GM tubes contains about 10% of halogen or organic gas, such as ethyl alcohol, which act as quenching gases. As the argon ions approach the cathode or when they hit it they may cause additional ionization which in turn causes additional erroneous pulses. As the ionization potentials of halogens and ethyl alcohol are lower than that of argon, Ar< | + | In addition to argon (or neon) the filling gas in GM tubes contains about 10% of halogen or organic gas, such as ethyl alcohol, which act as quenching gases. As the argon ions approach the cathode or when they hit it, they may cause additional |
| - | ions transfer their positive charges to them when hitting them. These in turn do not cause additional ionization and their positive charge is neutralized on the surface of the cathode. | + | |
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| ===== 10.4. Dead-time ===== | ===== 10.4. Dead-time ===== | ||
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| - | When recording high pulse rates in GM tubes and in proportional counter (as also in most other radiation detectors) one needs to take into account the dead-time. As the argon gas ionizes, the induced electrons travel very fast to the anode while the positive argon ions travel much slower which causes a very low electric field near the anode (Figure X.3). The detector is then unable to record pulses that are caused from new radiation absorption events due to the travel of argon ions towards the cathode and recovery of the filling gas back to argon atoms. The time when the detector cannot record new pulses is called dead-time and it is marked with $\tau$. | + | When recording high pulse rates in [[# |
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| - | When so high count rates are measured that the dead-time becomes important the observed count rates need to be corrected for dead-time $\tau$ (unit s). For that we mark observed count rate by $R$ (imp/s) and the true count rate by $R_0$ (imp/s) that would be observed if there was no dead-time. Because of the dead-time, $R_0 - R$ impulses in each second remain unrecorded. On the other in each second the tube is unable to record impulses a time $R \times \tau$ during which $R_0 \times R \times \tau$ photons or particles hit the detector. Thus | + | When so high count [[textbook: |
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| - | This equation can be used to correct the observed count rate to true count rate as far as the dead-time of the tube is known. For example, if the observed count rate is 1000 imp/s and the dead-time is 0.2 ms the true count rate is $\frac{1000}{1 - 1000 \times 0.0002} = 1250 \, \text{imp/ | + | This equation can be used to correct the observed |
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| - | In GM tubes the dead-time is 0.1-0.4 ms while in proportional counters it is much shorter, only a few microseconds. Therefore, a proportional counter can be used to measure a hundred times higher count rates without the essential effect of dead-time. If proportional counter is used not only for pulse counting but also for nuclear spectrometry the highest count rates should, however, be avoided since the tube has, in addition to dead-time, also a recovery time (Figure X.3). If a new particle is recorded during the recovery time the pulse height response of the tube is higher than | + | In [[textbook: |
| - | when each particle is recorded completely individually without overlap. The total recovery time in proportional counters is much higher than the dead-time, around 0.1 ms. | + | |
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| ===== 10.5. Use of Geiger-Műller and proportional counters ===== | ===== 10.5. Use of Geiger-Műller and proportional counters ===== | ||
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| - | Still in the 1950’s GM tubes were the most typical detectors for radiation measurements. For the activity measurements of individual radionuclides they needed to be first chemically separated from other radionuclides. Development of solid scintillation and semiconductor detectors have almost completely made chemical separation of gamma-emitting radionuclides unnecessary and thus also replaced gas ionization tubes in their measurements. Furthermore, | + | Still in the 1950’s |
| - | mostly replaced measurement of beta-emitting radionuclides with gas ionization detectors. The gas ionization detectors are, however, still in extensive use, especially in radiation protection for the measurement or radiation doses and dose rates as well as in detection of surface contamination. In addition, GM tubes can be used in teaching since they are cheap and easy to operate and instead of more sophisticated equipment they can be used to demonstrate some basic features in radiation measurements. Basically GM tubes can be used to measure all types of radiation. Gamma radiation is readily penetrating and counting efficiencies are only 1-2%. Thus GM tubes are used only for gamma dose and dose rate measurements. All beta and alpha particles entering the tube create electric pulse. However, to enter a tube the alpha and beta sources either need to be placed inside the tube or the window between the source and the tube should be very thin. For alpha radiation the thin window is made of plastics and these types of tubes are used to detect alpha contamination from various surfaces. For beta radiation the thin (0.1 mm) windows are made of mica, glass or beryllium but even these are too thick to allow measurement of the lowest beta energies, such 18 keV beta energies of tritium. Even though scintillation counting today is a standard method for beta counting, a gas ionization detector has one important advantage over it: the background is much lower which enables measurement of lower activities. An example of such equipment is the Risö | + | |
| Beta Counter (Figure X.4) which is a rather simple equipment and easy to operate. It has five sample positions for sources prepared after chemical separation and individual GM-tubes for each sample position. The samples are shielded against external radiation by lead shield and a guard counter that detects external radiation passing through the lead shield and subtracts the count rate observed in the guard detector from the total observed count rate. With this equipment the background count rate is typically only 0.2 cpm compared to at least ten times higher background | Beta Counter (Figure X.4) which is a rather simple equipment and easy to operate. It has five sample positions for sources prepared after chemical separation and individual GM-tubes for each sample position. The samples are shielded against external radiation by lead shield and a guard counter that detects external radiation passing through the lead shield and subtracts the count rate observed in the guard detector from the total observed count rate. With this equipment the background count rate is typically only 0.2 cpm compared to at least ten times higher background | ||
| observed with liquid scintillation counting. | observed with liquid scintillation counting. | ||
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| - | Neutrons as neutral particles do not cause any ionization in gas ionization detectors. To detect neutrons the tube is filled with BF< | + | //Neutrons as neutral particles do not cause any ionization in gas ionization detectors//. To detect neutrons the tube is filled with BF< |
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| - | and the emitted [[textbook: | + | and the emitted [[textbook: |
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email: mst@evalion.cz | tel: +420 224 358 331 | Copyright © 2021 A-CINCH
This project has received funding from the Euratom research and training programme 2019–2020 under grant agreement No. 945301.