ORACT: a 174-neutron-group activation cross-section library for fusion and fission reactor design studies

Abstract

A 174-neutron-group activation cross-section library for 233 ground-state target isotopes and 22 isomeric target isotopes is described. The library, ORACT, was derived from the ACTL Evaluated Neutron Activation Cross-Section Library and was developed for use with existing computer codes that calculate induced activation by convoluting the cross-section data with neutron scalar flux distributions. The activation cross sections extend over the energy range from thermal to MeV and are useful for fusion and fission reactor nuclear design studies as well as other applications.

Keywords

PLASMA PHYSICS AND FUSION TECHNOLOGY
REACTOR MATERIALS
DATA COMPILATION
RADIOACTIVATION
THERMONUCLEAR REACTOR MATERIALS
CROSS SECTIONS
NEUTRON REACTIONS
BARYON REACTIONS
DATA
HADRON REACTIONS
INFORMATION
MATERIALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA 700209* -- FUSION POWER PLANT TECHNOLOGY-- COMPONENT DEVELOPMENT & MATERIALS TESTING

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