Nuclear Safety

Appendix 4: Dose Calculations

A4-1 Introduction

This appendix gives some examples of dose calculations which have been used during discussions on conceptual designs of various plants. The dose calculations are of a simple type, suitable for indicative evaluations. More elaborate calculations are usually performed in the final phases of the safety analysis, when systems and components purchase specifications have already been defined.

A4-2 Virtual population dose in a severe accident

The following sections describe the virtual population dose for a future reactor (an order of magnitude evaluation in the short term, at three days, and in the long term, several years).

A4-2-1 The reactor and the released isotopes

The example is a passive type boiling water reactor of 600 MWe, provided with a double containment and a stack.

The quantities of isotopes chosen as guide isotopes in the core (1800 MWt) are, at equilibrium:

131I

1.85 10 18 Bq

137Cs

148 10 15 Bq

133Xe

3.7 10 18 Bq

85Kr

12.95 10 15 Bq

A4-2-2 Source term at three days (I, Cs, Xe)

  • The leakage rate assumed for the primary containment (taken into account the probability of leakage rates higher than the specified ones and possible damages to penetrations for severe accidents): 5 10% per diem.

  • The leakage rate assumed for the secondary containment room (systems, collection room or building): 1 10% per diem. (For this assumption to be valid extremely unlikely sequences are excluded, such as the rupture of a steam line with...

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