Fluoride-Cooled High-Temperature Pebble-Bed Reactor Reference Plant Model Updates
This work presents the latest improvements to, and investigations performed with, the Fluoride-Cooled High-Temperature Pebble-Bed Reactor reference plant models for the United States Nuclear Regulatory Commission. These models, developed with the Comprehensive Reactor Analysis Bundle, or BlueCRAB, serve as the foundation for the future development of detailed design evaluation models based on license applications. BlueCRAB […]
Gas-Cooled High-Temperature Pebble-Bed Reactor Reference Plant Model Updates
This work presents the latest improvements to, and investigations performed with, the pebble-bed high-temperature gas-cooled reactor (PB-HTGR) reference plant models for the United States Nuclear Regulatory Commission. These models serve as the foundation for the future development of detailed design evaluation models based on license applications. The reference plant models have been developed with the […]
High-Temperature Gas-Cooled Pebble-Bed Reactors Running In And Transient Modeling Capabilities Demonstration
This study presents a comprehensive benchmarking and verification effort of several thermal-hydraulic and multiphysics capabilities for high-temperature gas-cooled reactor (HTGR) applications. The first part of this effort focuses on the running-in verification of Griffin’s multiphysics capabilities, specifically for simulating the evolution of Pebble Bed reactor cores from startup to equilibrium. In the absence of validation […]
SAM: A Modern System Code for Advanced Non-LWR Safety Analysis
The System Analysis Module (SAM), developed at Argonne National Laboratory and by collaborators at other organizations, is for advanced non–light water reactor safety analysis. SAM aims to provide fast-running, modest-fidelity, whole-plant transient analysis capabilities that are essential for fast-turnaround design scoping and engineering analyses of advanced reactor concepts. To facilitate code development, SAM utilizes the […]
Code Validation of SAM Using Forced and Natural-Circulation Data from NACIE-UP Benchmark
Heavy liquid metals (HLMs) are promising candidates as coolants of Generation IV fast reactors due to their thermo-physical properties. In the last decade, experimental works have been proposed as part of Research & Development efforts to develop such systems. In this context, researchers from the Brasimone Research Center conducted many experiments using the Natural Circulation […]
Multiphysics Analysis of the MSRE Experiment Using Griffin-SAM Coupled Code System
Molten salt reactors (MSRs) with flowing fuel have the unique feature of utilizing the fuel salt for heat generation and extraction at the same time since the fuel salt is circulating through the whole primary loop of the reactor. This movement of the fuel salt results in a partial decay of the delayed neutron precursors […]
Code Benchmark of Depressurized Conduction Cooldown Transient in the High Temperature Test Facility
This paper presents results from modeling of a depressurized conduction cooldown (DCC) transient at the High Temperature Test Facility (HTTF) as part of the OECD-NEA Thermal Hydraulics Code Validation Benchmark for High-Temperature Gas-Cooled Reactors using HTTF Data . This paper briefly describes the benchmark and the models being used. It then presents a comparison of […]
Overview of Advanced Reactor Simulation Capabilities to Support Demonstrations
The Virtual Test Bed (VTB) was established to support the deployment of advanced reactors by facilitating the use of state-of-the-art modeling and simulation capabilities. These tools are able to solve previously prohibitive challenge problems in greater levels of fidelity and in a multi-physics framework. A VTB repository was recently set up to host models for […]
Modeling of HTTF test PG-26 using RELAP5-3D and SAM
Overview: HTTF PG-26 REALP5-3D Model Results SAM Model Results Conclusions