title: Analysis of the criteria used by the International Commission on Radiological Protection to justify the setting of numerical protection level values.
abstract: This report compiles the various numerical protection level values published by the International Commission on Radiological Protection (ICRP) since its 1990 Recommendations (Publication 60). Several terms are used to denominate the protection levels: individual dose limit, 'maximum' individual dose, dose constraint, exemption level, exclusion level, action level, or intervention level. The reasons provided by the Commission for selecting the associated numerical values is quoted as far as available. In some cases the rationale is not totally explicit in the original ICRP report concerned; in such cases the Task Group that prepared the present report have proposed their own interpretation. Originally, this report was prepared by a Task Group at CEPN, a French research and development center, in behalf of IRSN, a French public expert body engaged in radiological protection and nuclear safety. It is published here with kind permission by CEPN and IRSN.
mesh_terms: D004307:Dose-Response Relationship, Radiation; D004630:Emergencies; D004781:Environmental Exposure / Q000032:analysis / Q000517:prevention & control; D006801:Humans; D007390:International Agencies; D017744:Medical Waste Disposal; D016273:Occupational Exposure / Q000032:analysis / Q000517:prevention & control; D011829:Radiation Dosage; D011835:Radiation Protection / Q000592:standards*; D017751:Safety Management; D023481:Terrorism
chemical_list: D017744:Medical Waste Disposal