By Aspects of Design for Nuclear Powerplants (IAEA NS-G-1.13)
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Extra info for Radiation Protection
The equipment in treatment systems for solid, liquid and gaseous radioactive waste may contain radioactive material in high concentrations, and radiation protection from this material should be provided for site personnel. An estimate should be made of the expected radionuclide content in treated waste, and of the consequent maximum radiation level that can arise in each area of the waste treatment system. Consideration should be given to the sources that give rise to the highest radiation levels (such as ion exchange 10 Requirements and recommendations on the management of radioactive waste before it is sent to a repository are established in IAEA Safety Requirements and Safety Guides [4–6].
9 The dose rates may be calculated by using the source terms that are the basis for the radiation protection aspects of design (see Annexes II and IV), or they may be based on operating experience from similar plants provided that any changes in the relevant design and operating parameters are not significant. The zoning should be consistent with national legislation and regulatory requirements. It may be adequate to use the same definition of the zones as will be used when the plant is operational but it is found in many cases that a more specific definition of the zones is necessary for design purposes.
2. A simplified strategy for the reduction of exposures in the (dashed of a PWR). (5) (6) (7) Collective and individual doses should be evaluated by combining the results of steps 3 and 4. The use of a database is recommended. The maximum use should be made of relevant operational experience, where available, particularly for work that is difficult to predict such as unplanned maintenance. The proposed procedure is shown in the schematic flow chart of the factors that determine individual and collective doses in Fig.