A mixed formulation of the plane-stress problem to facilitate reuse of constitutive models in finite-element programs
The plane-stress assumption can be challenging to support in a finite element program because it traditionally requires separate implementations of constitutive models than those intended for three-dimensional or two-dimensional plane-strain simulations. As a solution to this issue, this paper presents a method to solve the plane-stress problem using a mixed formulation. In this formulation, the […]
Bayesian Calibration of Irradiated Graphite Property Models under High Temperatures
Graphite is a crucial material for advanced nuclear reactors such as very-high-temperature reactors, thermal molten-salt reactors, fluoride-salt-cooled high-temperature reactors, and various microreactors. Ensuring the long-term performance of graphite components under high temperature and irradiation with significant spatial gradients is essential for reactor safety and reliability. This paper addresses the modeling and prediction of key graphite […]
Review of recent activities with MOOSE, an open-source finite element & finite volume multi-fidelity simulation framework
Modeling and simulation are an increasing part of engineering. This is undoubtedly driven by the high costs of constructing experimental facilities, but also enabled by the exponential increase in computing powers over the last decades, which allows computational models to be closer than ever to reality. One of the main drivers for the development of […]
3.0 MOOSE: Enabling massively parallel multiphysics simulation
The development of MOOSE has kept accelerating since the last release, with over 2,100 pull requests merged over the last 30 months that involved nearly fifty contributors across close to a dozen institutions internationally. The growth in MOOSE’s capabilities and downstream applications is reflected in the growth of the community. User support provided on the […]
Multiphysics Demonstration of Temperature-Driven Assembly Bowing in SFRs using MOOSE-Based Codes
Core bowing is an important passive safety mechanism in liquid metal cooled fast reactors. When the core restraint system is properly designed, temperature and flux gradients influence assemblies in the core to bow into less reactive configurations during accident scenarios, resulting in negative reactivity feedback. Prediction of core bowing involves complex interplay of radiation transport, […]
Fitness-for-Service Analysis of Reactor Components under Flexible Load-Following Operating Conditions
Conventional power-generation plants, including nuclear plants, have been traditionally designed to provide a steady baseload energy capacity, optimizing output efficiency while minimizing variable costs. However, the growing adoption of large-scale renewable energy-generation systems, which rely on intermittent sources such as solar and wind, has introduced more variability into the energy supply in interconnected electricity grids. […]
Multiphysics simulation of recent experiments on alkali-silica reaction expansion in reinforced concrete members
Alkali-silica reaction (ASR) is an important degradation process that causes volumetric expansion and damage in concrete, and is affected significantly by the local temperature, moisture and stress conditions that often vary across the regions of a structure. Numerical simulation is essential to predict the progression and effects of ASR on the performance of structures. Because […]
Continuum Damage Mechanics Modeling Of High-Temperature Flaw Propagation: Application To Creep Crack Growth In 316H Standardized Specimens And Nuclear Reactor Components
Predicting creep crack growth (CCG) of flaws found during operation in high-temperature alloy components is essential for assessing the remaining lifetime of those components. While defect assessment procedures are available for this purpose in design codes, these are limited in their range of applicability. This study assesses the application of a local damage-based finite-element methodology […]
Preliminary Nuclear Containment Vessel Modeling for Multi-Hazard Probabilistic Risk Assessment under Seismic Hazards and Concrete Degradation
The current practice for natural phenomena hazards (NPH) risk assessment of nuclear facilities is to compute the risk for each hazard independently and then compound the total risk as a combination of single hazard risks. This state of practice does not consider correlations between hazards and the cascading impacts to structures, systems, and components (SSCs), […]
Integration Plan for NEAMS Structural Materials and Chemistry MSR Modeling
As part of its broad objective to support advanced reactor development, the US Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program has a strong interest in developing simulation capabilities to address chemistry and corrosion issues for molten salt reactors (MSRs). To that end, the Structural Materials & Chemistry (SMC) technical area within […]