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Title: The AMPX/SCALE Multigroup Cross-Section Processing for Fast Reactor Analysis

Conference ·

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1437912
Resource Relation:
Journal Volume: 132; Conference: PHYSOR 2018 - Cancun, , Mexico - 4/22/2018 4:00:00 AM-4/26/2018 4:00:00 AM
Country of Publication:
United States
Language:
English

References (7)

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data journal December 2011
Application of the Probability Table Method to Multigroup Calculations of Neutron Transport journal December 1974
Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods journal September 2004
Efficient Methods for the Treatment of Resonance Cross Sections journal October 1973
The Serpent Monte Carlo code: Status, development and applications in 2013 journal August 2015
Methods for Processing ENDF/B-VII with NJOY journal December 2010
A Probability Table Based Cross Section Processing System: CALENDF - 2001 journal August 2002

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