Artificial sources
In addition to natural background radiation, people are exposed to radiation from various man-made sources, the largest of which is the application of X rays in medical diagnosis. Although the doses delivered in different types of X-ray examinations vary from a small fraction of a mGy to tens of mGy (Table 7), the average annual dose per capita from medical and dental irradiation in developed countries of the world now approaches in magnitude the dose received from natural background radiation (Table 6). Less significant artificial sources of radiation include radioactive minerals in crushed rock, building materials, and phosphate fertilizers; radiation-emitting components of television sets, smoke detectors, and various other consumer products; radioactive fallout from nuclear weapons (Table 8); and radiation released in nuclear power production (Table 6).
| Worldwide dose commitment from radioactive fallout from nuclear tests prior to 1970* | |||
|---|---|---|---|
|
*North temperate zones; doses calculated for bone surface. **Calculated to year 2000 only. | |||
| source | isotope | half-life | due to bone surfaces (mGy) |
| external radiation |
short lived (e.g., iodine-131) |
8 days | 360 |
|
longer lived (e.g., cesium-137) |
30 years | 360 | |
| internal radiation | strontium-89 and -90 | 50 days | 1,310 |
| cesium-137 | 28 years | 210 | |
| carbon-14** | 5,730 years | 160 | |
| total | 2,400 | ||
|
Typical doses to exposed tissue received in routine X-ray diagnosis | |
|---|---|
| *Milligray is a unit of absorbed radiation dose; it corresponds to 1/1,000 joule of radiation energy absorbed per kilogram of tissue. | |
| examination | dose per exposure in milligray (mGy)* |
| X-ray photograph | |
| chest | 0.4–10 |
| abdominal | 10 |
| extremities | 2.5–10 |
| fluoroscopy | 100–200 per minute |
| X-ray movies | 250 per examination |
| CAT scan | 50–100 per examination |
Most of the radioactivity produced in nuclear power reactors is safely contained; however, a small percentage escapes as stack gas or liquid effluent and eventually may contaminate the atmosphere and water supply. (There are similar releases from nuclear-fuel reprocessing plants.) Though nuclear plants are basically clean sources of energy, they thus contribute to the worldwide background radiation level. This problem cannot be entirely avoided by using coal instead of nuclear fuel for power production, since many sources of coal contain natural radioactivity (e.g., radium) that is released in stack gases, along with chemical pollutants.
From Table 6 it is evident that the human population is now exposed to about twice as much radiation from all sources combined as it receives from natural sources alone. Hence, it is important to understand the possible consequences, if any, that may result from the additional exposure to radiation.
In comparison with the relatively small amounts of radiation described above, the dose typically administered to a patient in the treatment of cancer is thousands of times larger; i.e., a total dose of 50 Sv or more is usually delivered to a tumour in daily exposures over a period of four to six weeks. To protect the normal tissues of the patient against injury from such a large dose, as well as to protect medical personnel against excessive occupational exposure to stray radiation, precautions are taken to restrict exposure to the tumour itself insofar as possible. Comparable safeguards are utilized to minimize the exposure of workers employed in other activities involving radiation or radioactive material. Similarly, elaborate safety measures are required for disposal of radioactive wastes from nuclear reactors, due in part to the slow rate at which certain fission products decay. A given amount of plutonium-239, for example, still retains about one-half of its radioactivity after 25,000 years, so that reactor wastes containing this long-lived radionuclide must be safely isolated for centuries.
In the event of an atmospheric nuclear bomb explosion, large quantities of radioactivity are released, the dispersal of which depends on the prevailing weather conditions as well as on the height and nature of the blast. Although the level of contamination resulting from such an explosion or from a nuclear-power plant accident is generally highest in the immediate vicinity of the event itself, both radioactive gas and dust may be transported via air or water for many hundreds of kilometres and eventually contaminate the entire globe.
Mechanism of biologic action
As ionizing radiation penetrates living matter, it gives up its energy through random interactions with atoms and molecules in its path, leading to the formation of reactive ions and free radicals. It is the molecular alterations resulting from these ionizations and, in turn, the resultant biochemical changes that give rise to various types of injury. X rays and gamma rays, for example, impart their energy to “planetary” atomic electrons, which are thereby ejected from their orbits. Such an ejection of a planetary electron results in an ion pair consisting of a free electron and the electrically charged atom from which it was ejected. The ejected electron may give rise to a highly reactive free radical, which in turn may diffuse far enough to attack a biologically important target molecule in its vicinity. This so-called indirect action process, through which radiation causes damage via radiation-induced free radicals, may be envisioned as follows:
While the initial steps in the above process occur almost instantaneously, expression of the biologic effect may take years or decades, depending on the type of injury involved. The indirect action of radiation is more important in the biologic effects of low-LET radiations than in those of high-LET radiations (see above The passage of matter rays: Linear energy transfer and track structure), but the latter have a greater capacity to cause injury through direct interaction with biologic targets.
Direct biologic actions, studied in detail between 1927 and 1947, gave rise to a target theory of radiobiology that has provided a quantitative treatment of many of the biologic effects of radiation, particularly in the field of genetics. According to this theory, a tissue or cell undergoing irradiation is likened to a field traversed by machine-gun fire, in which the production of a given effect requires one or more hits by an ionized track on a sensitive target. The probability of obtaining the effect is thus dependent on the probability of obtaining the requisite number of hits on the appropriate target or targets.
The distribution of ionizing atomic interactions along the path of an impinging radiation depends on the energy, mass, and charge of the radiation. The ionizations caused by neutrons, protons, and alpha particles are characteristically clustered more closely together than are those caused by X rays or gamma rays. Thus, because the probability of injury depends on the concentration of molecular damage produced at a critical site, or target, in the cell (e.g., a gene or a chromosome), charged particles generally cause greater injury for a given total dose to the cell than do X rays or gamma rays; i.e., they have a high RBE. At the same time, however, charged particles usually penetrate such a short distance in tissue that they pose relatively little hazard to tissues within the body unless they are emitted by a radionuclide, or radioactive isotope, that has been deposited internally.
Radionuclides and radioactive fallout
Radionuclides emit various ionizing radiations (e.g., electrons, positrons, alpha particles, gamma rays, or even characteristic X rays), the precise types of which depend on the radionuclide in question. Exposure to a radionuclide and its emissions may be external, in which case the penetrating power of the radiation is an important factor in determining the probability of injury. Alpha particles, for example, do not penetrate deeply enough into the skin to cause damage, whereas energetic beta particles or X rays can be hazardous to the skin and deeper tissues.