ANS / Publications / Journals / Nuclear Technology

SAM: A Modern System Code for Advanced Non-LWR Safety Analysis

Rui Hu, Ling Zou, Daniel O’Grady, Travis Mui, Zhiee Jhia Ooi, Guojun Hu, Eric Cervi, Gang Yang, David Andrs, Alex Lindsay, Cody Permann, Robert Salko, Quan Zhou, Lambert Fick, Alexander Heald, Haihua Zhao

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1883-1902

Research Article / dx.doi.org/10.1080/00295450.2024.2409601

Thermal Fluid Modeling Approaches in SAM for High Temperature Gas-Cooled Reactor Applications

Ling Zou, Thanh Hua, Zhiee Jhia Ooi, Jun Fang, Rui Hu

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1903-1920

Research Article / dx.doi.org/10.1080/00295450.2024.2410623

Species Transport Framework Development in SAM for System-Level Tritium Source Term Analysis

Travis Mui, Rui Hu, Quan Zhou, Thanh Hua, Ling Zou

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1921-1936

Research Article / dx.doi.org/10.1080/00295450.2025.2503681

Implementation of a Drift Flux Model into SAM with Development of a Verification and Validation Test Suite for Modeling of Noncondensable Gas Mixtures

Robert K. Salko, Travis Mui, Ling Zou, Rui Hu

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1937-1959

Research Article / dx.doi.org/10.1080/00295450.2024.2370189

Multiphase Species Transport Modeling for Molten Salt Reactors in the System Analysis Module: Generation, Decay, Deposition, and Extraction of Insoluble Fission Products

Huihua Yang, Qiyun Cheng, Ling Zou, Rui Hu, Wei Ji

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1960-1985

Research Article / dx.doi.org/10.1080/00295450.2024.2421678

Verification and Demonstration of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications

Ling Zou, Quan Zhou, Dan O’Grady, Rui Hu, Alex Heald, Haihua Zhao

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1986-2002

Research Article / dx.doi.org/10.1080/00295450.2024.2377522

SAM Two-Phase Flow Model Development and Applications for Operational Transients in Advanced Reactors

Michael Gorman, Ling Zou, Rui Hu

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2003-2016

Research Article / dx.doi.org/10.1080/00295450.2025.2496596

Development and Experimental Validation of a Heat Transfer Model for Spilled Molten Salt Pools

Quan Zhou, Sara A. Thomas, Remi Le Thai

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2017-2044

Research Article / dx.doi.org/10.1080/00295450.2024.2392396

Verification of the SAM Code by Means of the Method of Manufactured Solutions: Application to Molten Salt Reactor Multiphysics Simulation

Eric Cervi, Sébastien Baudier, Ling Zou, Rui Hu

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2045-2069

Research Article / dx.doi.org/10.1080/00295450.2024.2338506

Validation of a Hybrid Domain Overlapping Coupling Between SAM and CFD Against the TALL-3D Transients

Aaron Huxford, Ling Zou, Rui Hu, Victor Petrov, Annalisa Manera

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2070-2087

Research Article / dx.doi.org/10.1080/00295450.2024.2352665

MSR Transient Simulation and MSRE Transient Benchmark with SAM and SPECTRA

Tingzhou Fei, Marek Stempniewicz, Fulvio Bertocchi, Visura Pathirana, Thanh Hua, Rui Hu, Ferry Roelofs

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2088-2104

Research Article / dx.doi.org/10.1080/00295450.2024.2337338

Code Validation of SAM Using Forced and Natural Circulation Data from NACIE-UP Benchmark

Victor Coppo Leite, Elia Merzari, Ling Zou

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2105-2120

Research Article / dx.doi.org/10.1080/00295450.2024.2377526

Numerical Simulation and Experimental Comparison of System Analysis Module 1D Mixing Model for Cold Shock Transients in the Gallium Thermal-Hydraulic Mixing Facility

Molly Ross, Ling Zou, Hitesh Bindra

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2121-2134

Research Article / dx.doi.org/10.1080/00295450.2024.2366738

SAM Code Validation for High Prandtl Number Flow in Molten Salt Natural Circulation Facility

Jadyn Reis, Yassin Hassan

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2135-2144

Research Article / dx.doi.org/10.1080/00295450.2025.2480974

Development of Heat Transfer Framework in Vertical Parallel Plate Geometry for High Prandtl Number Coolant and Preliminary Validation of Mixed Convection Regime for FHR Application

Alexander Heald, Floren Rubio, Haihua Zhao

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2145-2163

Research Article / dx.doi.org/10.1080/00295450.2025.2472520

Validation of a Countercurrent Gas Flow Model for Use in the Kairos Power System Analysis Module (KP-SAM) Code

John Lowd, III, Alexander Dueñas, Quan Zhou, Seth R. Cadell, Haihua Zhao

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2164-2188

Research Article / dx.doi.org/10.1080/00295450.2025.2463132

Neutronics and Thermo-Fluids Simulation of Generic Pebble-Bed Fluoride-Salt-Cooled High-Temperature Reactor

Jin Li, Thomas Downar, Volkan Seker, Dan O’Grady, Rui Hu, Nader Satvat, Shai Kinast

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2189-2205

Research Article / dx.doi.org/10.1080/00295450.2024.2381282

Development of Whole System Digital Twins for Advanced Reactors: Leveraging Graph Neural Networks and SAM Simulations

Yang Liu, Farah Alsafadi, Travis Mui, Daniel O’Grady, Rui Hu

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 2206-2223

Research Article / dx.doi.org/10.1080/00295450.2024.2385214