Utilization of NEUP Data for HTGR Thermal-Fluid Code Validation: A New Resource Platform
The high-temperature gas-cooled reactor (HTGR) is a Generation-IV advanced nuclear reactor design that has received significant attention due to its ability to generate high-temperature heat ranging from 750-950 °C. HTGR designs feature tri-structural isotropic (TRISO) fuel coated with ceramics, including carbon and silicon carbide, which allows for high-temperature operation while maintaining structural and fission product […]
VALIDATION, VERIFICATION, AND CALIBRATION THROUGH A CAUSAL LENS
This paper presents an alternative method based on causal inference to perform validation, verification, and calibration of simulation models. While classical validation and verification approaches focus on the identification of the associations between data elements using statistical and machine learning methods, the novel methods in this paper focus instead on the identification of causal relationships […]
PBNC Presentation: Dynamic Modeling of a Latent Heat Thermal Battery
Presentation detailing dynamic modeling progress on a heat pipe integrated thermal battery system.
HTGR Validation: NEUP Survey and Database – Data Reporting Standard for HTGR Thermal-Fluid Experiments
Since 2009, the U.S. Department of Energy (DOE) Office of Nuclear Energy’s Nuclear Energy University Program (NEUP) has been at the forefront of nuclear research, specifically concentrating on advancing high-temperature gas-cooled reactor (HTGR) technologies. By Fiscal Year 2024, NEUP has authorized 36 projects dedicated to HTGR research, each contributing significantly to the enhancement of our […]
A machine-learning-aided data recovery approach for predicting multi-material thermal behaviors in advanced test reactor capsules
Instrumented experiments conducted at test reactors are essential to the deployment of new advanced reactor systems. Designing new experiments and generating data on specific reactor conditions require significant investments in terms of both time and cost. Finite element analysis software can be used to create high-fidelity models of experiment environments in order to support the […]
Dynamic Modeling of Latent Heat Thermal Battery
A dynamic thermodynamic model is constructed in Modelica for the thermal battery portion of a heat pipe integrated thermal battery and is demonstrated using a shakedown test. The model is also leveraged to inform aspects of an experiment configuration. The theory section discusses modeling assumptions of the thermal battery system, establishes how melting and fusing […]
Numerical Evaluation of Effective Thermal Conductivity of PCM with Metal Foam Incorporating Buoyancy Effects for Thermal Energy Storage
The thermal energy storage (TES) system has the capability to efficiently preserve thermal energy directly derived from the energy source, minimizing any conversion losses. Especially latent heat storage offers distinct advantages, including a substantial increase in energy storage density and minimization of temperature fluctuations within the plants. However, the phase change material (PCM) employed in […]
Development of Data Reporting Standards for High-Temperature Gas-cooled Reactor (HTGR) Nuclear Energy University Program (NEUP) Thermal-Fluid Experiments
Since 2009, the U.S. Department of Energy (DOE) Office of Nuclear Energy’s Nuclear Energy University Program (NEUP) has been at the forefront of nuclear research, specifically concentrating on advancing high-temperature gas-cooled reactor (HTGR) technologies. By Fiscal Year 2023, NEUP has authorized 35 projects dedicated to HTGR research, each contributing significantly to the enhancement of our […]
Verification, Validation, and Calibration Through a Causal Lens
While typical validation and verification approaches focus on identifying the associations between data elements using statistical and machine learning methods, the novel methods in this paper focus instead on identifying causal relationships between data elements. Statistical and machine-learning-based approaches are strictly data-driven, meaning that they provide quantitative comparison measures between data sets without explicitly considering […]
HTGR Validation: NEUP Survey and Database Database Development for HTGR Thermal-Fluid Experiments
This set of slides is aimed to improve access to the High-Temperature Gas-cooled Reactor (HTGR) validation data and optimize the return on the significant investment made by DOE. Supported by the Advanced Reactor Technologies (ART) Gas-Cooled Reactor (GCR) program. Slides include information from FY2009 to FY2023, there are in total 35 DOE NEUP projects focusing […]