Benchmarking FFTF LOFWOS Test# 13 using SAM code: Baseline model development and uncertainty quantification

Simulation of the High Temperature Test Facility (HTTF) Core Using the 2D Ring Model with SAM

(2022) Zhiee Jhia Ooi et al.   NUCLEAR SCIENCE AND ENGINEERING

SAM-ML: Integrating data-driven closure with nuclear system code SAM for improved modeling capability

(2022) Yang Liu et al.   NUCLEAR ENGINEERING AND DESIGN

Progress in international best estimate plus uncertainty analysis methodologies

(2021) Robert P. Martin et al.   NUCLEAR ENGINEERING AND DESIGN

Propagating neutronic uncertainties for FFTF LOFWOS Test #13

(2021) Andy Rivas et al.   NUCLEAR ENGINEERING AND DESIGN

Code validation of SAM using natural-circulation experimental data from the compact integral effects test (CIET) facility

(2021) Ling Zou et al.   NUCLEAR ENGINEERING AND DESIGN

Uncertainty quantification for Multiphase-CFD simulations of bubbly flows: a machine learning-based Bayesian approach supported by high-resolution experiments

(2021) Yang Liu et al.   RELIABILITY ENGINEERING & SYSTEM SAFETY

Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13

(2021) Shibao Wang et al.   ANNALS OF NUCLEAR ENERGY

Thermal-hydraulic transient analysis of the FFTF LOFWOS Test #13

(2021) Vincenzo Narcisi et al.   NUCLEAR ENGINEERING AND DESIGN

Benchmark Analysis on Loss-of-Flow-without-Scram Test of FFTF Using Refined SAC-3D Models

(2021) Siyu Lyu et al.   Science and Technology of Nuclear Installations

Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data

(2021) Stefan Radman et al.   ANNALS OF NUCLEAR ENERGY

Benchmark Simulation of the Natural Convection Shutdown Heat Removal Test Facility Using SAM

(2020) B. Hollrah et al.   NUCLEAR TECHNOLOGY

Three-dimensional flow model development for thermal mixing and stratification modeling in reactor system transients analyses

(2019) Rui Hu   NUCLEAR ENGINEERING AND DESIGN

Validation and uncertainty quantification of multiphase-CFD solvers: A data-driven Bayesian framework supported by high-resolution experiments

(2019) Yang Liu et al.   NUCLEAR ENGINEERING AND DESIGN

Uncertainty quantification of two-phase flow and boiling heat transfer simulations through a data-driven modular Bayesian approach

(2019) Yang Liu et al.   INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER

Evaluation of public dose from FHR tritium release with consideration of meteorological uncertainties

(2019) Xiao Wu et al.   SCIENCE OF THE TOTAL ENVIRONMENT

Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver

(2018) Yang Liu et al.   NUCLEAR SCIENCE AND ENGINEERING

Heat transfer to liquid metal: Review of data and correlations for tube bundles

(2009) Konstantin Mikityuk   NUCLEAR ENGINEERING AND DESIGN