Alexander Lindsay’s research while affiliated with Idaho National Laboratory and other places

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Publications (34)


The MOOSE fluid properties module
  • Article

February 2025

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16 Reads

Computer Physics Communications

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Christopher Green

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Joshua Hansel

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[...]

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Alexander Lindsay

Figure 1: Schematics of the GPU build procedure.
Figure 5: Comparison of the convergence behavior of CPU and GPU calculations with PJFNK.
Figure 6: Comparison of the convergence behavior of CPU and GPU calculations with Newton.
Figure 9: libCEED Operator Decomposition[1].
Performance comparison of CPU and GPU calculations with PJFNK.

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Assessing Accelerator Library Integration in MOOSE
  • Technical Report
  • Full-text available

September 2024

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149 Reads

The Multiphysics Object-Oriented Simulation Environment (MOOSE) is a general purpose open source multiphysics framework supporting native finite element and finite volume discretizations as well as wrapping other libraries providing arbitrary computational capabilities. Due to its generality, it has experienced significant success. However, with recent changes in the landscape of computer architectures, most notably the growth of Graphics Processing Unit (GPU) computing, MOOSE must assess new technologies or else risk alienating customers interested in the benefits these technologies can offer. In that vein, we have assessed multiple accelerator libraries developed through the Exascale Computing Project (ECP), including Kokkos, libCEED, and the Modular Finite Element Methods (MFEM), and present our evaluation of these libraries as candidates for incorporation into the MOOSE framework.

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DEVELOPMENT OF A HI-STORM OVERPACK AND MPC-32 THERMAL-HYDRAULIC MODEL WITH THE MOOSE FRAMEWORK

November 2023

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16 Reads

The Proceedings of the International Conference on Nuclear Engineering (ICONE)

Nuclear power is a significant source of electricity in the United States, but the average U.S. nuclear power plant is around 40 years old. Safe management of spent nuclear fuel (SNF) is a key aspect of the back end of the nuclear fuel cycle, and SNF dry storage systems are increasing in popularity as they represent an effective solution in this area given the absence of a final disposal system. In particular, the spent fuel cask system (dry cask method) provides a feasible solution for maintaining SNF (~60 years) prior to the final disposal. The HI-STORM overpack and MPC-32 canister are the primary components of the HI-STORM 100 dry cask storage system. They remove heat from the system via natural circulation with no human intervention required. This characteristic provides passive heat removal while requiring little maintinence in dry cask storage systems. This project aims to validate and improve the capabilities of a thermal model of the MPC-32 canister and HI-STORM overpack, using the Multiphysics Object-Oriented Simulation Environment (MOOSE) based on the previous study of the author. MOOSE is an open-source framework developed by Idaho National Laboratory for multiscale, multiphysics simulations. This study will improve the capabilities of the thermal-hydraulic model of the HI-STORM dry cask storage system. The dry cask storage system often uses the chimney model to model the natural circulation of the air in the overpack storage systems. This study offers a new reliable and inclusive strategy for resolving issues pertaining to dry cask storage. The solution strategy eliminates the assumptions of Bernoulli equation in the chimney model. In this study, we investigate and demonstrate MOOSE’s thermal-hydraulics modeling capabilities on a dry cask problem, including the modeling of natural circulation, heat transfer, and porous flow. Additionally, we will demonstrate a validation case with the thermal model to evaluate the overall performance of the model.



Citations (15)


... Another study investigating a 300 MWt space reactor for nuclear thermal propulsion was unique in that it did not use point kinetics [8]. In comparing a hybrid PID controller that accounts for both power and reactivity in light of period-generated control [9], the present work uses a much higher-fidelity MOOSE [10] model that couples full dimensional neutronics and thermal hydraulics models of the reactor. In regard to optimization of control drum configurations in the HOLOS-Quad microreactor design, moth-flame optimization was shown to be a good real-time control strategy in comparison to five other optimization algorithms that were also studied [11]. ...

Reference:

Nuclear Microreactor Control with Deep Reinforcement Learning
3.0 - MOOSE: Enabling massively parallel multiphysics simulations
  • Citing Article
  • May 2024

SoftwareX

... The MOOSE repository hosts modules which serve as building blocks to many downstream applications. New modules were created for electromagnetics [9], transport of scalar quantities, optimization, and solid properties. The heat conduction module has been renamed as the heat transfer module to better describe its capabilities. ...

The MOOSE electromagnetics module
  • Citing Article
  • February 2024

SoftwareX

... The basic multidimensional flow model in SAM was merged into the MOOSE Navier-Stokes module. [29] A multiscale model has been developed to include an explicit pebble temperature model nested in the porous media model for pebble bed reactor applications. This model can predict the macroscopic (pebble bed) and microscopic (pebble) temperature distributions under both steady-state and transient conditions. ...

MOOSE Navier–Stokes module
  • Citing Article
  • July 2023

SoftwareX

... In addition to a FE discretization, a finite volume discretization of the classical Euler equations has recently been added to Pronghorn in order to increase convective stability and improve solver performance for high-speed flows. 40 Ongoing efforts are focused on extending this implementation to include Pronghorn's Navier-Stokes and frictiondominated models, and as such, all simulations performed in this work are based on the FEM. Finally, time integration with a wide variety of implicit and explicit schemes is available. ...

Finite Volume Discretization of the Euler Equations in Pronghorn
  • Citing Technical Report
  • June 2020

... The solution to the set of rate equations dictated by equation (2) is accomplished using the open-source code network solver Chemical ReAction NEtworks (CRANE) [36]. CRANE has previously been through a verification and validation process when coupled to fluid codes for low to atmospheric pressure plasma discharges [37][38][39][40]. CRANE uses tabulated energy dependent reaction rates calculated from BOLSIG+ [41]. ...

Verification and Validation of the Open-Source Plasma Fluid Code: Zapdos
  • Citing Article
  • June 2023

Computer Physics Communications

... Recently, a CCP test case for hybrid fluid-PIC simulations has also been proposed [16]. Other benchmark studies include PIC simulations of axial-azimuthal [17] and radial-axial [18] kinetic instabilities in partially magnetized plasmas, fluid simulations of atmospheric-pressure streamers [19], and method of manufactured solutions for DD models [20]. ...

Verification methods for drift-diffusion reaction models for plasma simulations

... Similarly, Abbasi et al. 26 recently utilized microscopic solvers in a novel multiscale framework to predict different transport phenomena throughout the entire length of a fuel cell. Despite the large volume of research that has been performed on microscale physical modelling of SOFCs, [22][23][24][25][27][28][29][30] it is mostly focused on conventional microstructure designs whose 3D reconstructions are acquired with tomography methods (FIB-SEM in particular). The potential for more ordered microstructure configurations, distinct from conventional structures typically produced through tape casting, 31 or screen printing 32 remains largely unexplored in this context. ...

2.0 - MOOSE: Enabling massively parallel multiphysics simulation

SoftwareX

... The third challenge relates to tritium extraction from the ceramic materials invessel, which is comprised of complex, multi-physics interactions due to a variety of factors including steep temperature gradients, radiation-induced defects that can act as traps, and complex chemistry of the system due to lithium burn-up and/or residual impurities in the sweep gas. Understanding and appropriately accounting for this tritium release is critical both from a safety and fuel cycle viability perspective (van der Laan et al. 2016;Simon et al. 2022;Cristescu & Draghia 2020). Lastly, the relatively large volume of ceramic breeder and multiplier required for breeding blankets in future power systems and the need for regular refueling in order to maintain breeding performance will necessitate safe and economical solutions for reprocessing and recycling, thus minimizing cost and waste (Leys et al. 2021 (Hernández & Pereslavtsev 2018;Gaisin et al. 2020;Zhou et al. 2019), and designs/design methodology (Shimwell et al. 2016;Sharafat et al. 2016;V. ...

Tritium Transport Modeling at the Pore Scale in Ceramic Breeder Materials Using TMAP8

IEEE Transactions on Plasma Science

... The software used for the FEA was the Multiphysics Object-Oriented Simulation Environment (MOOSE) developed by Idaho National Labs 47 . MOOSE has seen use in nuclear reactor safety studies 73,74 . It can solve FE problems in parallel, scalable up to 30,000 cores. ...

Characterization of the Finite Element CFD Capabilities in the Multiphysics Object Oriented Simulation Environment
  • Citing Article
  • May 2022

Journal of Nuclear Engineering and Radiation Science

... A mortar finite element framework was added to MOOSE and verified. Its usage on contact mechanics and gap heat transfer modeling has improved solver convergence and result quality in practical nuclear reactor simulations [3]. ...

A mortar thermomechanical contact computational framework for nuclear fuel performance simulation
  • Citing Article
  • May 2022

Nuclear Engineering and Design