This standard specifies the individual monitoring principle, monitoring method, monitoring plan for radiation workers’ internal exposure and basic requirements for the explanation of measurement result.
This standard is only applicable to individual monitoring for occupational internal exposure.
2 Terminologies and Definitions
For the purposes of this standard, the following terminologies and definitions apply.
2.1 Individual monitoring of internal exposure
It refers to the monitoring for the type and activity of radionuclides in body or excrement and the monitoring for the type and activity of radionuclides inhaled by the air sampler or respirator worn by workers (unless otherwise specified, hereinafter referred to as individual monitoring).
2.2 Intake
It refers to the quantity of radionuclides entering into body by inhalation and ingestion or via intact skin or wound.
2.3 Type F material
It refers to the material entering into body fluid from respiratory tract at fast absorption rate and all the material is absorbed into body fluid at a biological half-life of 10min.
2.4 Type M material
It refers to the material entering into body fluids from respiratory tract at medium absorption rate; 10% of the material is absorbed at a biological half-life of 10min and 90% of the material is absorbed at a biological half-life of 140d.
2.5 Type S material
It refers to the relatively insoluble material entering into body fluids from respiratory tract at slow absorption rate; 0.1% of the material is absorbed at a biological half-life of 10min and 99.9% of the material is absorbed at a biological half-life of 7 000d.
2.6 Personal air sampler (PAS)
It refers to a kind of portable unit specially designed for measuring the time integral activity concentration of airborne radioactive aerosol or gas in the respiratory zone of worker so as to assess the intake of the worker.
2.7 Static air sampler (SAS)
It refers to the device used to monitor the working space conditions and capable of providing useful data regarding the constitution and particle size of radionuclide.
2.8 Investigation level (IL)
It refers to the specified value of effective dose, intake or contamination level per unit area or unit volume, etc.; the investigation shall be carried out when reaching or exceeding this value.
2.9 Recording level (RL)