SCALE
Validation / Benchmark Reports
Spent Fuel Characterization and Decay Heat
Updates to the ORIGEN-S Data Libraries Using ENDF/B-VI, FENDL-2.0, and EAF-99 Data
ORNL/TM-2003/118
Isotopic Analysis of High-Burnup PWR Spent Fuel Samples From the Takahama-3 Reactor
ORNL/TM-2001/259
Strategies for Application of Isotopic Uncertainties in Burnup Credit
ORNL/TM-2001/257
MOX Cross-Section Libraries for ORIGEN-ARP
ORNL/TM-2003/2
ORIGEN-ARP Cross-Section Libraries for Magnox, Advanced Gas-Cooled, and VVER Reactor Designs
ORNL/TM-2003/263
Validation of the SCALE System for PWR Spent Fuel Isotopic Composition Analyses
ORNL/TM-12667
An Extension of the Validation of the SCALE (SAS2H) Isotopic Predictions for PWR Spent Fuel
ORNL/TM-13317
Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel
ORNL/TM-13315
Benchmark of SCALE (SAS2H)Isotopic Predictions of Depletion Analyses for San Onofre PWR MOX Fuel
ORNL/TM-1999/326
ARP: Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries
ORNL/TM-13584
Technical Support for a Proposed Decay Heat Guide Using SAS2H/ORIGEN-S Data
NUREG/CR-5625, ORNL-6698
Verification and Validation of the ORIGEN-S Code and Nuclear Data Libraries
RC-1429, COG-I-95-150
(Atomic Energy of Canada Limited (AECL) has approved posting of this document on the Oak Ridge National Laboratory SCALE website with the understanding that it has not been edited for wide publication. This report is not to be listed in abstract journals. If it is cited as a reference, the source from which copies may be obtained should be given as: Scientific Document Distribution Office (SDDO), AECL, Chalk River, Ontario, Canada K0J 1J0.)
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