ICRP Supporting Guidance 5
Analysis of the Criteria Used by the ICRP to Justify the Setting of Numerical Protection Level Values
Recommended citation
ICRP, 2006. Analysis of the Criteria Used by the ICRP to Justify the Setting of Numerical Protection Level Values. ICRP Supporting Guidance 5. Ann. ICRP 36 (4).
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 centre, on 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.
ICRP, 2006. Analysis of the Criteria Used by the ICRP to Justify the Setting of Numerical Protection Level Values. ICRP Supporting Guidance 5. Ann. ICRP 36 (4).
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 centre, on 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.
