ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
Version 6 of the SCALE (Standardized Computer Analyses for Licensing Evaluation) code system was released in February 2009. SCALE provides a comprehensive, integrated package of modular programs and nuclear data for a wide range of applications, including reactor physics, criticality safety, shielding, sensitivity/uncertainty analysis, and isotopic transmutation and radiation source term determination. SCALE computational modules are executed by automated control sequences that prepare input and call the desired modules in a particular order, linking output from one calculation to the next in series. The SCALE lattice physics sequence TRITON generates few-group, assembly-homogenized cross sections, as a function of burnup and branch states, which can be input to core simulator codes. TRITON couples the ORIGEN-S depletion module with either the NEWT (NEW Transport algorithm) two-dimensional (2D) arbitrary-geometry transport code or the three-dimensional Monte Carlo KENO code. Fluxes from the transport solution, along with self-shielded multigroup (MG) cross sections, are passed to ORIGEN-S, which computes the time-dependent isotopic concentrations of more than 1400 nuclides. One of the major advancements in SCALE 6 is the availability of new nuclear data libraries based on ENDF/B-VII for neutron transport calculations. In this paper we describe the SCALE ENDF/B-VII (designated here as V7) libraries and present some validation results for critical benchmarks and isotopic depletion experiments.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1026709
- Resource Relation:
- Conference: ANS Advances in Fuel Management Conference - Hilton Head, South Carolina, United States of America - 4/12/2009 12:00:00 AM-4/15/2009 12:00:00 AM
- Country of Publication:
- United States
- Language:
- English
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