FAKIR 6.0: A PC CODE FOR RESIDUAL DECAY HEAT, ACTIVITY AND DOSE RATE CALCULATION

Year
1998
Author(s)
J.C. Nimal - CEA/DRN/DMT/SERMA
T.D. Huynh - SOGEFI
C.M. Diop - CEA/DRN/DMT/SERMA
M. Messaoudi - Previously at SOGEFI
File Attachment
1821.PDF1.34 MB
Abstract
The knowledge of the residual activity, the decay heat power of irradiated fuel is needed in the different areas of the nuclear reactor industry. The neutron and gamma equivalent dose rate is also needed before shipping cask loading and transportation. The core physicist, the nuclear plant operator, the spent fuel conveyor and the safety authorities, all of them need data on residual activity and decay heat power. For this reason, the FAKIR calculation code has been developed, it takes into account the contribution of Fission Products, U239 + Np239 and Actinides. FAKIR is easy to use and provides good results of U02 and MOX fuel calculations, it has been developed by CEA. under EDF and COGEMA contracts as the standard method of calculation for both transport and storage of all PWR fuel assemblies received.