Whole-body counting

Last updated

In health physics, whole-body counting refers to the measurement of radioactivity within the human body. The technique is primarily applicable to radioactive material that emits gamma rays. Alpha particle decays can also be detected indirectly by their coincident gamma radiation. In certain circumstances, beta emitters can be measured, but with degraded sensitivity. The instrument used is normally referred to as a whole body counter.

Contents

This must not be confused with a "whole body monitor" which used for personnel exit monitoring, which is the term used in radiation protection for checking for external contamination of a whole body of a person leaving a radioactive contamination controlled area. [1]

Principles

Whole body monitor in use. WHOLE BODY COUNTER IS USED TO MEASURE NATURAL LEVELS OF RADIATION - NARA - 547319.tif
Whole body monitor in use.

If a gamma ray is emitted from a radioactive element within the human body due to radioactive decay, and its energy is sufficient to escape then it can be detected. This would be by means of either a scintillation detector or a semiconductor detector placed in close proximity to the body. Radioactive decay may give rise to gamma radiation which cannot escape the body due to being absorbed or other interaction whereby it can lose energy; so account must be taken of this in any measurement analysis. Whole-body counting is suitable to detect radioactive elements that emit neutron radiation or high-energy beta radiation (by measuring secondary x-rays or gamma radiation) only in experimental applications. [2]

There are many ways a person can be positioned for this measurement: sitting, lying, standing. The detectors can be single or multiple and can either be stationary or moving. The advantages of whole-body counting are that it measures body contents directly, does not rely on indirect bio-assay methods (such as urinalysis) as it can measure insoluble radionuclides in the lungs.

On the other hand, disadvantages of whole-body counting are that except in special circumstances it can only be used for gamma emitters due to self-shielding of the human body, and it can misinterpret external contamination as an internal contamination. To prevent this latter case scrupulous de-contamination of the individual must be performed first. Whole body counting may be unable to distinguish between radioisotopes that have similar gamma energies. Alpha and beta radiation is largely shielded by the body and will not be detected externally, but the coincident gamma from alpha decay may be detected, as well as radiation from the parent or daughter nuclides.

A scanning-bed whole-body counter. Scanning Bed WBC.JPG
A scanning-bed whole-body counter.

Calibration

A walk-in whole-body monitor with phantom (mannequin) for calibration. Stand-up WBC.JPG
A walk-in whole-body monitor with phantom (mannequin) for calibration.

Any radiation detector is a relative instrument, that is to say the measurement value can only be converted to an amount of material present by comparing the response signal (usually counts per minute, or per second) to the signal obtained from a standard whose quantity (activity) is well known.

A whole-body counter is calibrated with a device known as a "phantom" containing a known distribution and known activity of radioactive material. The accepted industry standard is the Bottle Manikin Absorber phantom (BOMAB). The BOMAB phantom consists of 10 high-density polyethylene containers and is used to calibrate in vivo counting systems that are designed to measure the radionuclides that emit high energy photons (200 keV < E < 3 MeV).

Because many different types of phantoms had been used to calibrate in vivo counting systems, the importance of establishing standard specifications for phantoms was emphasized at the 1990 international meeting of in vivo counting professionals held at the National Institute of Standards and Technology (NIST). [3] The consensus of the meeting attendees was that standard specifications were needed for the BOMAB phantom. The standard specifications for the BOMAB phantom provide the basis for a consistent phantom design for calibrating in vivo measurement systems. Such systems are designed to measure radionuclides that emit high-energy photons and that are assumed to be homogeneously distributed in the body.

Sensitivity

A well designed counting system can detect levels of most gamma emitters (>200 keV) at levels far below that which would cause adverse health effects in people. A typical detection limit for radioactive caesium (Cs-137) is about 40 Bq. The Annual Limit on Intake (i.e., the amount that would give a person a dose equal to the worker limit that is 20 mSv) is about 2,000,000 Bq. The amount of naturally occurring radioactive potassium present in all humans is also easily detectable. Risk of death by potassium deficiency approaches 100% as whole-body count approaches zero.

The reason that these instruments are so sensitive is that they are often housed in low background counting chambers. Typically this is a small room with very thick walls made of low-background steel (~20 cm) and sometimes lined with a thin layer of lead (~1 cm). This shielding can reduce background radiation inside the chamber by several orders of magnitude.

Count times and detection limit

Depending on the counting geometry of the system, count times can be from 1 minute to about 30 minutes. The sensitivity of a counter does depend on counting time so the longer the count, for the same system, the better the detection limit. The detection limit, often referred to as the Minimum Detectable Activity (MDA), is given by the formula:

...where N is the number of counts of background in the region of interest; E is the counting efficiency; and T is the counting time.

This quantity is approximately twice the Decision Limit, another statistical quantity, that can be used to decide if there is any activity present. (i.e., a trigger point for more analysis).

History

In 1950, Leonidas D. Marinelli developed and applied a low-level gamma-ray Whole Body Counter to measure people who had been injected with radium in the early 1920s and 1930s, contaminated by exposure to atomic explosions, and by accidental exposures in industry and medicine [4] [5] The sensitive methods of dosimetry and spectrometry Marinelli developed obtained the total content of natural Potassium in the human body. [6] [7] [8] [9] [10] [11] Marinelli's Whole Body Counter was first used at Billings Hospital at the University of Chicago in 1952. [12]

Related Research Articles

Background radiation is a measure of the level of ionizing radiation present in the environment at a particular location which is not due to deliberate introduction of radiation sources.

<span class="mw-page-title-main">Geiger counter</span> Instrument used for measuring ionizing radiation

A Geiger counter is an electronic instrument used for detecting and measuring ionizing radiation. It is widely used in applications such as radiation dosimetry, radiological protection, experimental physics and the nuclear industry.

<span class="mw-page-title-main">Neutron activation analysis</span> Method used for determining the concentrations of elements in many materials

Neutron activation analysis (NAA) is a nuclear process used for determining the concentrations of elements in many materials. NAA allows discrete sampling of elements as it disregards the chemical form of a sample, and focuses solely on atomic nuclei. The method is based on neutron activation and thus requires a neutron source. The sample is bombarded with neutrons, causing its constituent elements to form radioactive isotopes. The radioactive emissions and radioactive decay paths for each element have long been studied and determined. Using this information, it is possible to study spectra of the emissions of the radioactive sample, and determine the concentrations of the various elements within it. A particular advantage of this technique is that it does not destroy the sample, and thus has been used for the analysis of works of art and historical artifacts. NAA can also be used to determine the activity of a radioactive sample.

<span class="mw-page-title-main">Scintillation counter</span> Instrument for measuring ionizing radiation

A scintillation counter is an instrument for detecting and measuring ionizing radiation by using the excitation effect of incident radiation on a scintillating material, and detecting the resultant light pulses.

A radioactive tracer, radiotracer, or radioactive label is a synthetic derivative of a natural compound in which one or more atoms have been replaced by a radionuclide. By virtue of its radioactive decay, it can be used to explore the mechanism of chemical reactions by tracing the path that the radioisotope follows from reactants to products. Radiolabeling or radiotracing is thus the radioactive form of isotopic labeling. In biological contexts, experiments that use radioisotope tracers are sometimes called radioisotope feeding experiments.

<span class="mw-page-title-main">Radioactive contamination</span> Undesirable radioactive elements on surfaces or in gases, liquids, or solids

Radioactive contamination, also called radiological pollution, is the deposition of, or presence of radioactive substances on surfaces or within solids, liquids, or gases, where their presence is unintended or undesirable.

The measurement of ionizing radiation is sometimes expressed as being a rate of counts per unit time as registered by a radiation monitoring instrument, for which counts per minute (cpm) and counts per second (cps) are commonly used quantities.

<span class="mw-page-title-main">Gamma spectroscopy</span> Quantitative study of the energy spectra of gamma-ray sources

Gamma-ray spectroscopy is the qualitative study of the energy spectra of gamma-ray sources, such as in the nuclear industry, geochemical investigation, and astrophysics. Gamma-ray spectrometry, on the other hand, is the method used to acquire a quantitative spectrum measurement.

<span class="mw-page-title-main">Gamma counter</span> Instrument to measure gamma activity

A gamma counter is an instrument to measure gamma radiation emitted by a radionuclide. Unlike survey meters, gamma counters are designed to measure small samples of radioactive material, typically with automated measurement and movement of multiple samples.

In the measurement of ionising radiation the counting efficiency is the ratio between the number of particles or photons counted with a radiation counter and the number of particles or photons of the same type and energy emitted by the radiation source.

<span class="mw-page-title-main">Radioactivity in the life sciences</span>

Radioactivity is generally used in life sciences for highly sensitive and direct measurements of biological phenomena, and for visualizing the location of biomolecules radiolabelled with a radioisotope.

The formation evaluation gamma ray log is a record of the variation with depth of the natural radioactivity of earth materials in a wellbore. Measurement of natural emission of gamma rays in oil and gas wells are useful because shales and sandstones typically have different gamma ray levels. Shales and clays are responsible for most natural radioactivity, so gamma ray log often is a good indicator of such rocks. In addition, the log is also used for correlation between wells, for depth correlation between open and cased holes, and for depth correlation between logging runs.

<span class="mw-page-title-main">Bomab</span>

The BOttle MAnnequin ABsorber phantom was developed by Bush in 1949 and has since been accepted in North America as the industry standard for calibrating whole body counting systems.

Nuclear MASINT is one of the six major subdisciplines generally accepted to make up Measurement and Signature Intelligence (MASINT), which covers measurement and characterization of information derived from nuclear radiation and other physical phenomena associated with nuclear weapons, reactors, processes, materials, devices, and facilities. Nuclear monitoring can be done remotely or during onsite inspections of nuclear facilities. Data exploitation results in characterization of nuclear weapons, reactors, and materials. A number of systems detect and monitor the world for nuclear explosions, as well as nuclear materials production.

<span class="mw-page-title-main">Survey meter</span>

Survey meters in radiation protection are hand-held ionising radiation measurement instruments used to check such as personnel, equipment and the environment for radioactive contamination and ambient radiation. The hand-held survey meter is probably the most familiar radiation measuring device owing to its wide and visible use.

Internal dosimetry is the science and art of internal ionising radiation dose assessment due to radionuclides incorporated inside the human body.

<span class="mw-page-title-main">Radiation monitoring</span> Measurement of radiation doses or contamination

Radiation monitoring involves the measurement of radiation dose or radionuclide contamination for reasons related to the assessment or control of exposure to radiation or radioactive substances, and the interpretation of the results.

<span class="mw-page-title-main">Radiation portal monitor</span> Passive radiation detection device

Radiation Portal Monitors (RPMs) are passive radiation detection devices used for the screening of individuals, vehicles, cargo or other vectors for detection of illicit sources such as at borders or secure facilities. Fear of terrorist attacks with radiological weapons spurred RPM deployment for cargo scanning since 9/11, particularly in the United States.

<span class="mw-page-title-main">Leonidas D. Marinelli</span> American radiologist (1906–1974)

Leonidas D. Marinelli was the American radiological physicist who is best known for founding the field of Human Radiobiology and developing the Marinelli Beaker.

<span class="mw-page-title-main">Radioactive source</span>

A radioactive source is a known quantity of a radionuclide which emits ionizing radiation, typically one or more of the radiation types gamma rays, alpha particles, beta particles, and neutron radiation.

References

  1. Operational Monitoring Good Practice Guide - The Selection of Alarm Levels for Personnel Exit Monitors. Industry Radiological Protection Coordination Group, NPL, UK, Dec 2009.
  2. Oliver Meisenberg, Werner Buchholz, Klaus Karcher, Patrick Woidy, Udo C. Gerstmann: Measuring the internal activity of the neutron emitter 252Cf in-vivo: Basics and potentials based on measurements in phantoms. Radiation Physics and Chemistry 176, 2020, article no. 109087.
  3. Kramer GH and Inn KGW. "A Summary of the Proceedings of the Workshop on Standard Phantoms for In-Vivo Radioactivity Measurement". Health Physics 61(6) (1991), pp.893-894.
  4. Marinelli, L.D. 1956. The use of Na-T1 crystal spectrometers in the study of gamma-ray activity in vivo: A summary of developments at the Argonne national laboratory. Brit. Journ. of Radiol. Supplement 7 (Nov.): 38-43. (London Brit. Inst. Of Radiology)
  5. Berlman, I.B. and Marinelli L.D. 1956. “Twin” scintillation fast neutron detector. Rev. Sci. Instr. 27(10) (June 25): 858-859
  6. Miller, C.E., and L.D. Marinelli. 1956. The gamma-ray activity of contemporary man. Science, 124 (3212) (July 20): 122-123
  7. Berlman, I.B. and Marinelli L.D. June 25, 1956. “Twin” scintillation fast neutron detector. Rev. Sci. Instr. 27(10): 858-859
  8. Gustafson, P.F., L. D. Marinelli, and E. A. Hathaway. 1957. A case of accidental puncture contaminated with thorium-227: Studies on elimination and residual body activity. Radiology 68(3) (March): 358-365
  9. Marinelli, L.D. Nov. 1958. Radioactivity and the human skeleton. The Janeway Lecture. Am. J. Roentgenol. & Ra. Therapy and Nuclear Medicine, 80(5):729-739
  10. L.D. Marinelli (with Supplement by H.A. May). 1961. The use of low-level gamma scintillation spectrometry in the measurements of activity in human beings. Radioactivity in Man. Ed. H. Meneely, C. C. Thomas, Springfield, IL: 16-30
  11. May, H.A. and L.D. Marinelli. 1962. Sodium iodide systems: Optimum crystal dimensions and origin of background. Proceedings of the Symposium on Whole Body Counting, June 12-16, 1961. International Atomic Energy Agency, Vienna: 15-40
  12. Hasterlik, R. J. and L.D. Marinelli. 1955. Physical Dosimetry and clinical observations on four human beings involved in an accidental critical assembly excursion. Conference on the Peaceful Uses of Atomic Energy, Geneva, Switzerland (June 18.) Vol 11: Biological Effects of Radiation: 25-34. United Nations, N.Y. 1956