Status of the NEAMS and ARC neutronic fast reactor tools integration to the NEAMS Workbench
The Workbench initiative was launched in FY-2017 within the Nuclear Energy Advanced
Modeling and Simulation (NEAMS) Integration Product Line to facilitate the transition from …
Modeling and Simulation (NEAMS) Integration Product Line to facilitate the transition from …
Nuclear data uncertainty propagation applied to the versatile test reactor conceptual design
Abstract The Versatile Test Reactor (VTR) currently under development is a 300 MWth
sodium-cooled fast reactor (SFR) fueled with ternary metal alloy fuel, which aims to …
sodium-cooled fast reactor (SFR) fueled with ternary metal alloy fuel, which aims to …
Propagating neutronic uncertainties for FFTF LOFWOS Test# 13
The safety evaluation conducted for licensing a Sodium-cooled Fast Reactor (SFR) may
require modeling transients with best-estimate calculation tools that must first be validated …
require modeling transients with best-estimate calculation tools that must first be validated …
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead‐Cooled Fast Reactors
In this study, the Best Estimate Plus Uncertainty (BEPU) approach is developed for the
systematic quantification and propagation of uncertainties in the modelling and simulation of …
systematic quantification and propagation of uncertainties in the modelling and simulation of …
[PDF][PDF] Uncertainty quantification of ABR transient safety analysis-nuclear data uncertainties
Safety evaluation conducted for licensing a Sodium-cooled Fast Reactor (SFR) may require
modeling unprotected transients with best estimate calculation tools associated with …
modeling unprotected transients with best estimate calculation tools associated with …
ARDP Natrium Neutronic Methodology: Argonne Neutronic Assessment of ABR-1000
N Stauff, T Fei, M Smith - 2022 - osti.gov
The Natrium Sodium-cooled Fast Reactor (SFR) concept developed by TerraPower, LLC
was selected as one of the advanced reactor designs for demonstration under the Advanced …
was selected as one of the advanced reactor designs for demonstration under the Advanced …
Status of the NEAMS and ARC fast reactor tools integration to the NEAMS Workbench
The Workbench initiative was launched in FY-2017 within the Nuclear Energy Advanced
Modeling and Simulation (NEAMS) program to facilitate the transition from conventional …
Modeling and Simulation (NEAMS) program to facilitate the transition from conventional …
ARC integration into the NEAMS Workbench
N Stauff, N Gaughan, T Kim - 2017 - osti.gov
One of the objectives of the Nuclear Energy Advanced Modeling and Simulation (NEAMS)
Integration Product Line (IPL) is to facilitate the deployment of the high-fidelity codes …
Integration Product Line (IPL) is to facilitate the deployment of the high-fidelity codes …
[PDF][PDF] Sensitivity Analysis and Uncertainty Quantification of FFTF Cycle 8C using the NEAMS Workbench
This paper summarizes the sensitivity analysis and uncertainty quantification performed on
the global reactivity feedback coefficients of the Fast Flux Test Facility (FFTF) Cycle 8C core …
the global reactivity feedback coefficients of the Fast Flux Test Facility (FFTF) Cycle 8C core …
[PDF][PDF] Design of a mixed-spectrum long-lived reactor with improved proliferation resistance
A Abou Jaoude - 2017 - researchgate.net
I would like to start by thanking Dr. Erickson for her guidance and support throughout these
past four years. I was very fortunate to be given freedom to explore different ideas and think …
past four years. I was very fortunate to be given freedom to explore different ideas and think …