Aspects of operational radiation protection during dismantling of nuclear facilities relevant for the estimation of internal doses.
Operational radiation protection of workers during the dismantling of nuclear facilities is based on the same radiation protection principles as that applied in its exploitation period with the objective of ensuring proper implementation of the as-low-as-reasonably-achievable (ALARA) principle. These principles are: prior determination of the nature and magnitude of radiological risk; classification of workplaces and workers depending on the risks; implementation of control measures; monitoring of zones and working conditions, including, if necessary, individual monitoring. From the experiences and the lessons learned during the dismantling processes carried out in Spain, several important aspects in the practical implementation of these principles that directly influence and ensure an adequate prevention of exposures and the estimation of internal doses are pointed out, with special emphasis on the estimation of internal doses due to transuranic intakes.
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Subdirección de Protección Radiológica Operacional, Consejo de Seguridad Nuclear, C/Justo Dorado Dellmans 11, 28040 Madrid, Spain. tlm@csn.es
D006801:Humans; D009688:Nuclear Reactors; D016273:Occupational Exposure / Q000032:analysis*; D011829:Radiation Dosage; D011832:Radiation Injuries / Q000517:prevention & control; D011834:Radiation Monitoring / Q000379:methods*; D011835:Radiation Protection / Q000379:methods*; D018570:Risk Assessment; D013030:Spain