Estimated Radiation Doses Due to the Nuclear Fuel Cycle

Estimated Radiation Doses Due to the Nuclear Fuel Cycle 

An assessment of the potential hazard due to the release of radioactive material has to take account of the following parts of the nuclear fuel cycle (i) mining and fabrication of fuel, (ii) operation of power reactors, (iii) reprocessing of fuel (if desired), and (iv) disposal of wastes. 

The following discussion is based on a number of recent studies, the most important of which are those by E. E. Pochin (1976) and by the Study Group of the American Physical Society (1978). Details of these publications are given in the Bibliography. 

The estimated rates at which these isotopes are released from nuclear power plants are based on operating experience with a large number of reactors. The release rate will depend on the reactor type, power level, turbine and containment design, and population density around the plant. Of the four isotopes, the one whose release rates are most uncertain is since its significance for the long-term radiation dose has been appreciated only rather recently. 

The total integrated radiation dose from reactor operation has to be evaluated in terms of two components the dose to the public and the 

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