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ERANOS 2.1 : International Code System for GEN IV Fast Reactor Analysis
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2006
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New ReleaseEngineeringNuclear PhysicsInternational Code SystemNuclear DataEranos 2.1Nuclear Reactor DesignReactor AnalysisSystems EngineeringModeling And SimulationNuclear ReactorsHardware-in-the-loop SimulationNeutron SourceComputer EngineeringBenchmark ExperimentsNuclear EngineeringNuclear PowerNuclear Reactor EngineeringNuclear SafetyReactor SafetyNeutron ScatteringEranos Code
The paper introduces the new release of the European Reactor Analysis Optimized code System, ERANOS 2.1. ERANOS 2.1 includes all functions needed for reference and design calculations of Liquid Metal Fast Reactors, with extended capabilities for advanced fuel subassemblies and Gas Cooled Fast Reactors, and incorporates recent neutron data libraries such as JENDL‑3.3, JEFF‑3.1, and forthcoming ENDF/B‑VII. The updated code has been developed and validated to provide a reliable basis for neutronic calculations of current and advanced fast reactor cores in the GEN IV International Forum. Authors: not listed.
The aim of the paper is to present the new release of the European Reactor Analysis Optimized code System, ERANOS 2.1. This version has been developed and validated to establish a suitable basis for reliable neutronic calculations of current, as well as advanced fast reactor cores of the GEN IV International Forum. The latest version of the ERANOS code and data system, ERANOS 2.1, contains all of the functions required for reference and design calculations of Liquid Metal Fast Reactors (LMFR's), with extended capabilities for treating advanced reactor fuel subassemblies and cores of Gas Cooled Fast Reactors (GCFR's). The releases of recent, modern neutron data libraries: JENDL-3.3 in 2002, JEFF-3.1 in 2005 and soon ENDF/B-VII are also available. (authors)