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Title: POINT 2015: ENDF/B-VII.1 Final Temperature Dependent Cross Section Library

Version 00 For use in applications the ENDF/B-VII.1 library has been processed into the form of temperature dependent cross sections at eight neutron reactor like temperatures, between 0 K and 2100 K, in steps of 300 K (the exception being 293.6 K, for exact room temperature at 20 Celsius). It has also been processed to five astrophysics like temperatures—1, 10, and 100 eV; and 1 and 10 keV. For reference purposes, 300 K is approximately 1/40 eV, so that 1 eV is approximately 12,000 K. At each temperature the cross sections are tabulated and linearly interpolable in energy.
Publication Date:
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Report Number(s):
POINT2015; 004587MLTPL00
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Owner Installation: International Atomic Energy Agency Contributors: International Atomic Energy Agency, IAEA, Vienna, Austria. The latest ENDF/B-VII.1 data library is now freely available through the National Nuclear Data Center (NNDC), Brookhaven National Laboratory. This release completely supersedes all preceding releases of ENDF/B. The ENDF/B-VII.1 data library was processed into the form of temperature dependent cross sections and is being distributed as POINT2012. Details on this and previous versions of this library can be found in the included documentation. Compared to VII.0 which included 393 evaluations, VII.1 is comprised of 423 evaluations; this includes 32 new evaluations; 2 natural evaluations were dropped (23-V – Nat, and 30-Zn-Nat). See documentation for full list. As distributed the original evaluated data includes cross sections represented in the form of a combination of resonance parameters and/or tabulated energy dependent cross sections, nominally at 0 K. For use in applications, this data has been processed using the 2012 version of the ENDF/B pre-processing codes PREPRO 2015 to produce temperature dependent, linearly interpolable in energy, tabulated cross sections, in the ENDF-6 format. See Abstract for the steps required and codes used to produce room temperature, linearly interpolable tabulated cross sections, in the ENDF-6 format. KEYWORDS: BASED ON ENDF/B-VII.1; EVALUATED NEUTRON CROSS SECTIONS
Research Org:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
Contributing Orgs:
Not Specified
Country of Publication:
United States

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