Abstract
Production and validation of PMAXS library for fast and quasi transients with SARCS (Shiraz University Advanced Reactor Cross Section) is the main objective of this research. For this purpose, we developed SARCS FORTRAN 90 subroutines to utilize WIMSD5 lattice code and to generate PMAXS format cross sections. Verification of the generated library for fast transient is carried out for rod ejection and compared with Bushehr Nuclear Power Plant (BNPP) final Safety assessment report (FSAR). BNPP core depletion calculation during its first cycle at normal operation is considered as the quasi-transient. Neutronics Album of BNPP is used for quasi-transient verification.
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