The generation of broad-group working cross section libraries for nuclear fission reactor shielding and radiation damage applications in different spectral environments (LWR, SFR, LFR, HTR, etc.) is recommended in order to permit the use, in particular, of the three-dimensional (3D) deterministic transport codes in the data validation activities. 3D deterministic transport analyses could be performed, in parallel with similar 3D Monte Carlo analyses, on single-material and engineering neutron shielding benchmark experiments, included in the SINBAD (ORNL/RSICC - OECD/NEA Data Bank) international database. This action, mainly performed by the national research institutes, would be very useful not only for the reactor physicist and nuclear engineer data validation interests but also for the nuclear safety authorities and the industrial organizations.
Data Processing and Validation Needs of Group-Wise Working Cross Section Libraries for Nuclear Fission Reactor Shielding and Radiation Damage Applications
Pescarini, M.
2009-12-16
Abstract
The generation of broad-group working cross section libraries for nuclear fission reactor shielding and radiation damage applications in different spectral environments (LWR, SFR, LFR, HTR, etc.) is recommended in order to permit the use, in particular, of the three-dimensional (3D) deterministic transport codes in the data validation activities. 3D deterministic transport analyses could be performed, in parallel with similar 3D Monte Carlo analyses, on single-material and engineering neutron shielding benchmark experiments, included in the SINBAD (ORNL/RSICC - OECD/NEA Data Bank) international database. This action, mainly performed by the national research institutes, would be very useful not only for the reactor physicist and nuclear engineer data validation interests but also for the nuclear safety authorities and the industrial organizations.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
