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9. RADIATION PROTECTION

9.6. Radiation waste management

— Exempt waste (EW). Waste that meets the criteria for clearance, exemption or exclusion from regulatory control for radiation protection purposes.

— Very short lived waste (VSLW). Waste that can be stored for decay over a limited period of up to a few years and subsequently cleared according to arrangements approved by the regulatory authority, for uncontrolled disposal, use or discharge. This would include radioactive waste containing primarily radionuclides with short half-lives often used for research and medical purposes.

— Very low level waste (VLLW). Waste which does not meet the criteria as EW, but which does not need a high level of containment and isolation and therefore is suitable for disposal in near surface landfill type facilities, with limited regulatory control. Such landfill type facilities may also contain other hazardous waste. Typical waste in this class would include soil and rubble with low activity concentration.

— Low level waste (LLW). Waste that contains material with radionuclide content above clearance levels, but with limited amounts of long lived radioactivity. It requires robust isolation and containment for periods of up to a few hundred years and is suitable for disposal in engineered near surface facilities. It covers a very broad range of materials that includes short lived radionuclides at high activity levels, but long lived radionuclides only at relatively low activity levels.

— Intermediate level waste (ILW). Waste which, because of its content, particularly of long lived radionuclides, requires a higher level of containment and isolation than is provided by near surface disposal.

However, it needs no or only limited provision for heat dissipation during its storage and disposal. It may include long lived radionuclides, in particular alpha emitting radionuclides, that will not decay to an activity level acceptable for near surface disposal during the time which

institutional controls can be relied upon and therefore requires disposal at greater depths of the order of tens up to a few hundred metres.

— High level waste (HLW): Waste with radioactivity levels high enough to generate significant quantities of heat by the radioactive decay process or with large amounts of long lived activity which need to be considered in the design of a disposal facility for such waste. Disposal in deep (usually several hundred metres or more below the surface), stable geological formations is the generally recognized option for its long term management.

Most of the waste generated at an accelerator facility will fall into the categories of short lived, low level or intermediate level waste. The main sources of these wastes will be spent targets, chemicals used in the processing of targets and separation of radioisotopes from the target materials. Usually, this material can be collected on-site at a specific facility or in a designated area.

The radioactive waste should then be transferred to an authorized or licensed handler for removal from the site.

9.6.1. Decay in storage

One aspect of the short-lived radioactive isotopes is ‘decay in storage’

where the materials are allowed to decay to a low level in a shielded area before they are removed for disposal. During this time the amount of radioactive material may significantly decrease depending on the half-lives of the radioisotopes present, and in some cases the material may be discarded as regular waste if certain conditions are met. Normally, a facility may hold by-product material with a physical half-life of less than 120 days for decay in storage before disposal without regard to its radioactivity if the facility:

— Monitors by-product material at the surface before disposal and determines that its radioactivity cannot be distinguished from the background radiation level with an appropriate radiation detection survey meter set on its most sensitive scale and with no interposed shielding.

— Removes or obliterates all radiation labels, except for radiation labels on materials that are within containers and that will be managed as biomedical waste after they have been released from the licensee.

9.6.2. Protection of the general public

One of the most serious concerns is the protection of the general public from releases of radioactivity. Therefore, concentrations of radioactive material which may be released to the general environment must be below certain levels, defined set by regulatory control of radioactive discharges to the environment. Any radioactivity released in ground water, surface water, air, soil, plants, or animals must not result in an annual dose exceeding an equivalent of 250 mSv to the whole body, 750 mSv to the thyroid, and 250 mSv to any other organ of any member of the public. A reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment.

BIBLIOGRAPHY

INTERNATIONAL ATOMIC ENERGY AGENCY, Radiation Protection and the Safety of Radiation Sources, Safety Series No. 120, IAEA, Vienna (1996).

FOOD AND AGRICULTURE ORGANIZATION OF THE UNITED NATIONS, INTERNATIONAL ATOMIC ENERGY AGENCY, INTERNATIONAL LABOUR ORGANISATION, OECD NUCLEAR ENERGY AGENCY, PAN AMERICAN HEALTH ORGANIZATION, WORLD HEALTH ORGANIZATION, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, Safety Series No. 115, IAEA, Vienna (1996).

INTERNATIONAL ATOMIC ENERGY AGENCY, Assessment of Occupational Exposure due to External Sources of Radiation, IAEA Safety Standards Series No. RS-G-1.3, IAEA, Vienna (1999).

INTERNATIONAL ATOMIC ENERGY AGENCY, Assessment of Occupational Exposure due to Intakes of Radionuclides, IAEA Safety Standards Series No. RS-G-1.2, IAEA, Vienna (1999).

INTERNATIONAL ATOMIC ENERGY AGENCY, Calibration of Radiation Protection Monitoring Instruments, Safety Reports Series No. 16, IAEA, Vienna (1999).

INTERNATIONAL ATOMIC ENERGY AGENCY, The Management System for Facilities and Activities, IAEA Safety Standards Series No. GS-R-3, IAEA, Vienna (2006).

INTERNATIONAL ATOMIC ENERGY AGENCY, Application of the Concepts of Exclusion, Exemption and Clearance, IAEA Safety Standards Series No. RS-G-1.7, IAEA, Vienna (2004).

INTERNATIONAL ATOMIC ENERGY AGENCY, Regulatory Control of Radioactive Discharges to the Environment, IAEA Safety Standards Series No. WS-G-2.3, IAEA, Vienna (2000).

INTERNATIONAL ATOMIC ENERGY AGENCY, Intervention Criteria in a Nuclear or Radiation Emergency, Safety Series No. 109, IAEA, Vienna (1994).

INTERNATIONAL ATOMIC ENERGY AGENCY, Health Surveillance of Persons Occupationally Exposed to Ionizing Radiation: Guidance for Occupational Physicians, Safety Reports Series No. 5, IAEA, Vienna (1998).

INTERNATIONAL ATOMIC ENERGY AGENCY, Diagnosis and Treatment of Radiation Injuries, Safety Reports Series No. 2, IAEA, Vienna (1998).

INTERNATIONAL ATOMIC ENERGY AGENCY, Planning the Medical Response to Radiological Accidents, Safety Reports Series No. 4, IAEA, Vienna (1998).

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, General Principles for the Radiation Protection of Workers, Publication 75, Pergamon Press, Oxford and New York (1997).

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Recommendations of the International Commission on Radiological Protection, Publication 60, Pergamon Press, Oxford and New York (1991).

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Conversion Coefficients for Use in Radiological Protection Against External Radiation, Report of the Joint Task Group, Publication 74, ICRP, ICRU, Pergamon Press, Oxford and New York (1997).

INTERNATIONAL COMMISSION ON RADIATION UNITS AND MEASUREMENTS, Quantities and Units in Radiation Protection Dosimetry, Rep. No. 51, ICRU, Bethesda (1993).

INTERNATIONAL COMMISSION ON RADIATION UNITS AND MEASUREMENTS, Measurement of Dose Equivalents from External Photon and Electron Radiations, Rep. No. 47, ICRU, Bethesda (1992).

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Protection Against Radon-222 at Home and at Work, Publication 65, ICRP, Pergamon Press, Oxford and New York (1993).

INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Dose Coefficients for Intakes of Radionuclides by Workers, Publication 68, ICRP, Pergamon Press, Oxford and New York (1994).

INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, Quality Management and Quality Assurance Standards, Part 1: Guidelines for Selection and Use, ISO 9000-1, ISO, Geneva (1994).

INTERNATIONAL ORGANIZATION FOR STANDARDIZATION, INTERNATIONAL ELECTROTECHNICAL COMMISSION, General Requirements for the Competence of Calibration and Testing Laboratories, ISO/IEC Guide 25, IEC, Geneva (1990).

INTERNATIONAL LABOUR OFFICE, Radiation Protection of Workers (ionizing radiations), and ILO Code of Practice, ILO, Geneva (1987).

OECD NUCLEAR ENERGY AGENCY, Work Management in the Nuclear Power Industry: A Manual for the NEA Committee on Radiation Protection and Public Health by the ISOE Expert Group on the Impact of Work Management on Occupational Exposure, OECD, Paris (1997).

OECD NUCLEAR ENERGY AGENCY, Considerations on the Concept of Dose Constraint: A Report by a Joint Group of Experts from the OECD Nuclear Energy Agency and the European Commission, OECD, Paris (1996).

UNITED NATIONS, Sources and Effects of Ionizing Radiation: 1993 Report to the General Assembly with Scientific Annexes, UN, New York (1993).