Occupational Intakes of Radionuclides Part 1 - ICRP

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3554 3555 3556 3557 3558 3559 DRAFT REPORT FOR CONSULTATION included. For the skeleton, all activity in trabecular and cortical bone (both surface and volume) and in bone marrow is included. (c) In the dose per unit content functions for bioassay samples, the dose per unit content for a 24 h sample of urine or faeces is provided. The sample activity is decaycorrected to the time of the end of the sampling period. 102
3560 3561 3562 3563 3564 3565 3566 3567 3568 3569 3570 3571 3572 3573 3574 3575 3576 3577 3578 3579 3580 3581 3582 3583 3584 3585 3586 3587 3588 3589 3590 3591 3592 3593 3594 3595 3596 3597 3598 3599 3600 3601 3602 DRAFT REPORT FOR CONSULTATION 4 METHODS OF INDIVIDUAL AND WORKPLACE MONITORING 4.1 Introduction (246) This Chapter briefly describes the main measurement techniques, their advantages and their limitations for individual monitoring. In most cases, assessment of intakes of radionuclides may be achieved by body activity measurements, excreta monitoring, air sampling with personal air samplers, workplace measurements or a combination of these techniques. The choice of measurement technique will be determined by a number of factors including the radiation emitted by the radionuclide, the availability of equipment, the biokinetic behaviour of the contaminant and the likely radiation dose. 4.2 Body Activity Measurements (In Vivo Measurements) (247) In vivo measurement of body or organ content provides a quick and convenient estimate of activity in the body. It is performed with one or more photon detectors placed at specific positions in relation to the subject being measured. It is feasible only for those radionuclides emitting radiation that can be detected outside the body. In principle, the technique can be used for radionuclides that emit: X or radiation: positrons, since they can be detected by measurement of annihilation radiation; or energetic b particles that can be detected by measurement of Bremsstrahlung radiation (e.g. 90 Y, produced by the decay of its 90 Sr parent). (248) The detectors used for in vivo measurements are usually partially shielded and the individual to be measured can be placed in a shielded, low background room to reduce the interference from ambient sources of radiation. (249) Direct (in vivo) bioassay is likely to be the monitoring method of choice if the radionuclide is a high yield, high energy gamma-ray emitter or decays by positron emission (with emission of annihilation radiation), unless the material is excreted rapidly from the body. The gamma-radiation emitted by such radionuclides is strongly penetrating, and so is readily detected using scintillation or semiconductor detectors positioned close to the body. If the material is absorbed rapidly from the respiratory tract, and is then either distributed uniformly in body tissues (e.g. 137 Cs in most common chemical forms), or is distributed preferentially among a number of organs, (e.g. 59 Fe) then whole body monitoring should be chosen. If the radionuclide deposits preferentially in a single organ such as the thyroid (e.g. 125 I, 131 I), then partial body monitoring of the relevant organ should be chosen. In the case of materials that are absorbed less rapidly from the respiratory tract (e.g. insoluble forms of 60 Co oxide), lung monitoring is preferable to whole body monitoring soon after the intake, as it gives a more accurate measure of lung deposition and retention than a whole body measurement. (250) Direct bioassay is also useful for some radionuclides that emit photons (X- or -rays) at lower energies and/or with lower yields (e.g. 241 Am, 210 Pb, 144 Ce). However, in the case of radionuclides that mainly emit X-rays below 25 keV with low yields (notably, the alpha-emitting isotopes of plutonium and curium) direct bioassay may not achieve the sensitivity required for radiological protection purposes. 103
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Occupational Intakes of Radionuclides Part 1 - ICRP

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