Overview of the SAS4A metallic fuel models and extended analysis of a postulated severe accident in the prototype gen-IV sodium-cooled fast reactor
The SAS4A safety analysis code, originally developed for the analysis of postulated severe
accidents in oxide fuel sodium-cooled fast reactors (SFRs), has been significantly extended …
accidents in oxide fuel sodium-cooled fast reactors (SFRs), has been significantly extended …
Initial Core Physics and Safety Analyses Supporting the Versatile Test Reactor
T Sumner, F Heidet, TH Fanning, C Grandy, T Fei… - 2018 - osti.gov
The Versatile Test Reactor (VTR) is a proposed integrated facility for investigations into the
behavior of fuels and materials subjected to high, fast neutron fluxes prototypical of fast …
behavior of fuels and materials subjected to high, fast neutron fluxes prototypical of fast …
Validation of Advanced Metallic Fuel Models of SAS4A using TREAT MSeries Overpower Test Simulations
A Karahan, A Tentner - 2017 - inis.iaea.org
The SAS4A safety analysis code has been extended to include mechanistic and physics-
based models of U-Pu-Zr and U-Zr metallic fuel pins. The simulation of various phenomena …
based models of U-Pu-Zr and U-Zr metallic fuel pins. The simulation of various phenomena …
ОБЗОР ЗАРУБЕЖНЫХ РАСЧЕТНЫХ КОДОВ ДЛЯ МОДЕЛИРОВАНИЯ АВАРИЙ С ОТКАЗОМ АВАРИЙНОЙ ЗАЩИТЫ ПРИМЕНИТЕЛЬНО К БЫСТРЫМ …
ВВ Андреев, ММ Африн - Научно-технический вестник Поволжья, 2020 - elibrary.ru
В работе представлен краткий обзор расчетных кодов, используемых для
моделирования аварийных ситуаций на АЭС. В данном исследовании в качестве …
моделирования аварийных ситуаций на АЭС. В данном исследовании в качестве …
Fast Reactor Methods Development Plan
TH Fanning, MA Smith, AJ Brunett - 2018 - osti.gov
Fast reactor design and safety analysis methods (computer codes) have been under
development for approximately sixty years. During the first forty years, code development …
development for approximately sixty years. During the first forty years, code development …