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 […]
Status of New Models Hosted on the Virtual Test Bed (VTB) in 2024
The National Reactor Innovation Center (NRIC) mission is to support deployment of novel reactor concepts. This is achieved by providing physical and virtual spaces for building and testing various components, systems, and complete pilot plants. The Virtual Test Bed (VTB) represents the virtual counterpart to the physical test bed. It is in development in collaboration […]
Studies of the Influence of Heat Pipe Model and Coupling Strategy in Heat Pipe Microreactor Simulations Using Sockeye
This work demonstrates several modeling approaches of thermal fluids phenomena in heat pipes and the thermal coupling of the heat pipe to a graphite monolithic block in a microreactor context, taking into account the presence of a gap between the two. We show that the selection of the heat pipe model has a significant impact […]
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 […]
Reduce-Order Modeling of Multigroup Neutron Cross Sections for High-Temperature Gas-cooled Reactors
Deterministic neutronics calculations rely on multigroup neutron cross section libraries, which usually consists of a database of tabulated values, used to calculate the cross sections through multivariate linear interpolation. However, interpolation of the multidimensional cross section data becomes memory inefficient and time consuming as the number of tabulations increases, significantly slowing down the neutronics calculation, […]
Multiphysics Running-In Simulations for Pebble-Bed Reactors with Griffin
Griffin, a Multiphysics Object-Oriented Simulation Environment (MOOSE)–based application targeting transient modeling of advanced reactors, has been used recently to model pebble-bed reactors (PBRs). The modeling effort has focused thus far on equilibrium core calculations. A new capability to simulate the running-in phase of PBR operation has been added to Griffin. This work demonstrates the new […]
The Monolithic Heat Pipe Microreactor Reference Plant Model
This work introduces a reference plant model for a generic monolithic heat-pipe-cooled microreactor. The model will serve as a springboard to develop future evaluation models in the licensing process of similar microreactor designs at the U.S. Nuclear Regulatory Commission. This model has been developed with the Comprehensive Reactor Analysis Bundle and its specifications are based […]
Generating An Advanced Cross-section Library For HTGR Pebble Bed Depletion Calculations Using Reduced-Order Model Generation Techniques
For code development, Advanced Reactor Technologies – Gas Cooled Reactors Program (ART-GCR) rely on a collaboration with the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, but the cross sections generation and the methodology definition is part of this program area goals. Based on previous studies in FY23, the size of microscopic cross section libraries […]
Reduced-Order Modeling of Multigroup Neutron Cross Sections for High-Temperature Gas-cooled Reactors
Abstract – Deterministic neutronics calculations rely on multigroup neutron cross section libraries, which consist of databases of tabulated values, used to calculate the neutron cross sections through multivariate linear interpolation. However, interpolation of the multidimensional cross section data becomes memory inefficient and time consuming as the number of tabulations increases, significantly slowing down the neutronics […]
Sodium-Cooled Fast Reactor Reference Plant Model
This report details the progress of INL on the creation of a reference plant multiphysics model for the ABTR. The model was developed within Task 13 of the NRC project “Development and Modeling Support for Advanced Non-Light Water Reactors” and is an extension of the reference plant developed in Task 4b. Several improvements were made […]