کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1740469 | 1521755 | 2015 | 9 صفحه PDF | دانلود رایگان |

• Development of a new and convenient method to generate PMAXS cross section library.
• The PMAXS library is extended for fast and quasi-fast transient analysis in LWRs.
• Verification of generated PMAXS formatted Cross section library.
• Development of a GUI for automatic generation of PMAXS library for hexagonal lattice.
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.
Journal: Progress in Nuclear Energy - Volume 83, August 2015, Pages 347–355