This section provides information for guidance purposes.
Accelerators used for industrial radiography produce photons in the MeV range at high dose rates. For example, a 3 MV-Linatron accelerator can produce a dose rate of 3 Gy per minute at 1 metre and a similar device operating at 9 MV can yield a dose rate of 30 Gy per minute at the same distance (16).
High-energy (MeV) photons can interact with atomic nuclei, causing nuclei transformation and release of energy in the form of photons or energetic particles or a combination of both. One such particle can be a neutron. The interaction process is called photodisintegration. This reaction is energetically feasible whenever the photon energy exceeds the binding energy of a proton or neutron in the atom nucleus. For materials heavier than hydrogen, except beryllium, the photon threshold energy for such reactions is generally >5 MeV (17) . For accelerators operating at <6 MV, the neutron yield from photodisintegration reactions would be extremely low and therefore would not be a concern as a radiation hazard (18).
This procedure normally employs radioactive-based sources. The procedure, practice or radiation source is beyond the scope of this Safety Code.
Industrial x-ray equipment may occasionally be used for purposes other than industrial radiography. In a facility in which this is the case, it is the responsibility of the industrial x-ray machine owner in that facility to (a) ensure that individuals using the x-ray equipment for non-radiography purposes have the appropriate education, training and competence; and (b) determine the individuals' suitability for the particular job intended.
Radiation safety education should be consistent with that of a Radiation Safety Course, such as the one administered by the NDE Institute of Canada (19) or equivalent. The training and education should include:
The RSO shall identify the subset of industrial x-ray equipment users who are engaged in non-radiography work, and ensure that they have the necessary education and training and have demonstrated competence before undertaking the job in question. Except for the certification criterion, the requirements of Section 2.3 of this Safety Code shall apply to that subset of industrial x-ray machine users.
Personnel monitoring devices are needed to record and control whole-body exposures to ensure occupational limits are not exceeded in accordance with the ICRP recommendations (Appendix II of this Safety Code). For external dose monitoring purposes, devices should be worn on the clothing closest to the body either at the waist or chest level. Patented and state-of-the-art personnel monitoring systems, capable of registering and reporting dose levels as low as 0.01 mSv, are readily available (12) ; older technology also exists (13). As a general guide to users of ionizing radiation sources, it is extremely important to notify your dosimetry service provider of the radiation sources you are using or likely to use, seek the appropriate passive dosimeters, and ensure that your occupational doses reported, correctly reflect the contribution from the various radiation sources you are using.
Industrial radiographers and other users must wear photon-sensitive passive dosimeters as well as instantaneous reading electronic alarm dosimeters. Each passive personal dosimeter must be worn by only one individual. It is advised that passive detectors be stored in a secure, properly shielded location between periods of use to avoid registering exposures from extraneous sources. Personnel monitoring data need to be retained as a permanent record and be made readily available for review by industrial radiography personnel, other users of the equipment and the regulatory authority.
Computation of occupational doses for purposes of assessment against worker dose limits recommended by the ICRP (refer to Appendix II in this Safety Code) must be based on the summation of all exposures incurred by the individual from the ionizing radiation sources used in industrial radiography. Photon-sensitive passive detectors collectively record x-ray and gamma-ray components. Natural background radiation or medical radiation contributions are not computed as occupational exposures.
An electronic personnel dosimeter not only provides direct dose reading capability, but also is designed to emit an audible signal intended to provide instantaneous feedback to its wearer about the radiation conditions prevailing in an area. The alarm set point may be for a dose rate or an integrated dose. Electronic alarm dosimeters shall (i) be checked to ensure proper functioning before use; (ii) be set to give an alarm at a preset dose equivalent rate of 5 mSv/h or an integrated dose of 2 mSv(14) , with an accuracy of ± 20 %of the true radiation dose; (iii) be calibrated at periods not exceeding 12 months; and (iv) require special means to change the preset alarm function. Following activation of the alarm, the dosimeter wearer is obligated to exercise appropriate radiation control measures to reduce his or her occupational dose. Such dosimeters work reasonably well for conventional x-ray (and gamma-ray) sources. However, there are radiation sources that produce very high x-ray levels in a time frame in the order of microseconds (e.g., flash x-ray sources (20) ) and the electronic personnel dosimeter may not have sufficient time to respond within that time frame; this sub-optimal dosimeter response could be falsely interpreted to mean the absence of x rays. Thus, an alternative dosimeter that provides direct dose reading display capability should be used, provided that it has been tested to provide reliable results and the wearer must be aware of any inherent limitations thereof. Direct dose-reading dosimeter results shall be recorded for individual wearers.
To avoid underestimation of the exposure rate from industrial x-ray equipment, the cross-sectional area of the radiation beam must be larger than the sensitive area of the survey meter detector. For routine survey work the meter should yield readings that are accurate to ± 20%.The energy response should be flat to within ± 20% over the desired photon energy range to be encountered. Survey meters that utilize an ionization chamber must be calibrated over the energy range for which they are to be used; calibration factors shall be used to convert the meter readings to appropriate dose values. A meter having several measurement ranges provides greater flexibility. A meter that provides maximum scale readings in the range of 10 µSv/h to 10 mSv/h (or the equivalent in exposure or dose units) is suggested. The detector response time must be short enough for an accurate radiation measurement. The meter must not exhibit "fold-back"
under any circumstances. Fold-back is said to occur when an instrument is exposed to an exposure (or dose) rate or cumulative exposure (or absorbed dose) in excess of its display range and shows a lower or zero reading. Ideally, a meter that is designed against fold-back should show an off-scale deflection or, in the case of a digital display, show an overload condition when it is exposed to ionizing radiation fields that exceed the measurement range. In work areas where radio frequency (RF) fields might be present ensure that the survey meter is not sensitive to the ambient RF fields (by wrapping the meter in metallic gauze).
Several web sites may be consulted regarding radiation protection instrumentation (21) .
Unintentional exposure to radiation may be caused by equipment failure or human error or a combination of both. Radiation accident victims must receive prompt medical attention by a physician. In addition, the root cause of the incident must be investigated and remedial measures taken to prevent recurrence at the facility. To address such situations, the facility is responsible for developing an emergency response plan and having the capabilities to implement the plan. Personnel must be trained to handle emergency equipment and to follow written procedures. The plan shall be tested and validated, and deficiencies shall be identified and corrected. The facility needs to liaise with the various personnel identified in the emergency procedures.
As a guide, the generic emergency response plan should include:
The facility shall prepare a written report that contains: a description of the accident; methods used to protect other workers and the public; assessments of exposures to the accident victims, workers, emergency services personnel and members of the public; cause of the accident and corrective actions. That report shall be submitted (by the RSO) to the regulatory authority for review and follow up within 5 calendar days after the incident (see Section 2.2.1.23. of this Safety Code).
X-ray equipment intended for resale shall also comply with the REDAct and regulations at time of sale. The seller is responsible for
If the purchaser's facility is under federal jurisdiction, the Nonmedical X-Ray Unit, Consumer and Clinical Radiation Protection Bureau, Health Canada shall be contacted and the facility shall adopt this Safety Code. Otherwise, the appropriate provincial or territorial radiation protection authority shall be contacted to determine the applicable operational requirements for the x-ray machine.
For the disposal of an x-ray machine, the RSO shall observe the instructions provided by the manufacturer in the product manual or contact the manufacturer for information and guidance. In a case where a manufacturer is no longer in the business of manufacturing, selling or servicing industrial x-ray equipment, the following procedures shall be followed: