Michael Jarrett

ORCID: 0000-0003-1834-0719
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About
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Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Nuclear and radioactivity studies
  • Graphite, nuclear technology, radiation studies
  • Advanced Numerical Methods in Computational Mathematics
  • Nuclear Physics and Applications
  • Semiconductor Quantum Structures and Devices
  • Solar Radiation and Photovoltaics
  • Sepsis Diagnosis and Treatment
  • Artificial Intelligence in Healthcare and Education
  • Gas Dynamics and Kinetic Theory
  • Geophysical Methods and Applications
  • Energy, Environment, and Transportation Policies
  • Radiative Heat Transfer Studies
  • Management and Organizational Studies
  • Advanced Semiconductor Detectors and Materials
  • Radioactive element chemistry and processing
  • Heat transfer and supercritical fluids
  • Advancements in Semiconductor Devices and Circuit Design
  • Semiconductor materials and devices
  • Ionosphere and magnetosphere dynamics
  • Particle accelerators and beam dynamics
  • Groundwater flow and contamination studies
  • Machine Learning in Healthcare
  • Real-time simulation and control systems

Argonne National Laboratory
2021-2022

University of Michigan
2012-2020

CEA Cadarache
2016

Direction des énergies
2016

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2016

The coarse-mesh finite difference (CMFD) method is one of the most widely used methods for accelerating convergence numerical transport solutions. However, in some situations, iterative using CMFD can become unstable and fail to converge. We present evaluate three different modifications scheme that provide enhanced stability: multiple sweeps, artificial diffusion, relaxing flux update. Fourier analysis on each these schemes an idealized problem characterize stability rate both fixed-source...

10.13182/nse16-51 article EN Nuclear Science and Engineering 2016-09-09

The lower bounds for the theoretical convergence rate of variants Coarse Mesh Finite Difference (CMFD) method neutron transport acceleration are studied in this paper by generalization into three categories: artificially diffusive CMFD, flux relaxation, and higher-order spatial prolongation operators. A Fourier analysis methods demonstrates that artificial diffusion relaxation mathematically equivalent arbitrarily scale coarse mesh to fine projection (CMP) vector. high-order is shown affect...

10.1080/00295639.2017.1293408 article EN Nuclear Science and Engineering 2017-05-10

We study the influence of various types contacting media and contact area on current-fluctuation level in semiconductors, testing supposition that electronic noise is governed, part, by phonon-leaking dynamics to environment. Using passivated gettered silicon PIN diodes as experimental test-beds, presented data lends credence prediction phonon-refraction characteristics semiconductor-metal interface substantially impacts current fluctuations solid. Specifically, if one implements metallic...

10.1109/tns.2013.2266798 article EN IEEE Transactions on Nuclear Science 2013-07-04

The Two-Dimensional (2-D)/One-Dimensional (1-D) method allows pin-resolved computational transport solutions for large, full-core light water reactor simulations at relatively low cost compared to a true three-dimensional (3-D) method. 2-D/1-D constructs an approximation the 3-D equation with (1) 2-D in radial variables and , discretized on fine spatial grid, (2) 1-D (or approximate PN) axial variable radially coarse grid. equations are coupled through transverse leakage (TL) terms. In this...

10.1080/00295639.2018.1507186 article EN Nuclear Science and Engineering 2018-09-19

Successful operation of the Versatile Test Reactor (VTR) relies on satisfying stakeholder requirements and guaranteeing customer timelines. Although VTR leverages proven sodium fast reactor technology, its mission as a test introduces unique design operational requirements. This paper covers preliminary analysis methodology development for two areas core related to flexibility necessary testing mission. The first these framework assessing feasibility storing used driver fuel in shield...

10.1080/00295639.2022.2031712 article EN cc-by-nc-nd Nuclear Science and Engineering 2022-03-21

We study the influence of various types contacting media and contact area on current-fluctuation level in semiconductors, testing supposition that electronic noise is governed, part, by phonon-leaking dynamics to environment. Using passivated gettered silicon PIN diodes as experimental test-beds, presented data lends credence prediction phonon-refraction characteristics semiconductor-metal interface substantially impacts current fluctuations solid. Specifically, if one implements metallic...

10.1109/nssmic.2012.6551956 article EN 2012-10-01

A new method for calculating anisotropic radial transverse leakage (TL) in a two-dimensional (2D)/one-dimensional (1D) transport is derived and implemented MPACT. This makes use of parity the polar angle only to form 2D equations 2D/1D method. The even-parity component solved on fine mesh using characteristics (MOC), while odd-parity coarse S N. TL cell boundaries calculated by combining even- components. faster than similar previous because it delegates half work required calculate solution...

10.1080/00295639.2019.1627176 article EN Nuclear Science and Engineering 2019-07-22

Two-dimensional/one-dimensional (2D/1D) methods have become popular for solving the 3D Boltzmann neutron transport equation on medium-to-large computing platforms. These can a wide range of accuracy that depends largely fidelity coupling between 2D and 1D solutions in spatial angular variables. In general, with higher-order are both more accurate computationally expensive. order to simplify reduce computation, an isotropic term is frequently used. The deficiency this approximation compared...

10.1080/23324309.2020.1819330 article EN Journal of Computational and Theoretical Transport 2020-09-18

The primary mission of the Versatile Test Reactor (VTR) is to provide peak fast flux in excess 4.0 x 10 15 n/cm 2 -s support fuel and material testing. To achieve a high flux, it beneficial maximize peaking center core. With single enrichment zone, highly peaked distribution produces power distribution. Coolant inlet orifices can be designed handle but orifice design simplified if more even radial achieved. An approach reduce factor use zoning, which would improve coolant flow homogeneity....

10.1051/epjconf/202124712007 article EN cc-by EPJ Web of Conferences 2021-01-01

The Versatile Test Reactor (VTR) is expected to operate in a persistent non-equilibrium state due inter-cycle variations experimental loading. goal of planning and optimizing the fuel loading for this mode operation can differ from equilibrium cycle optimization. In work, general algorithm core reload fast reactor with respect some objective function developed. used work preliminary model that defined capture most parameters be interest, but elements could added or subtracted as needed...

10.1051/epjconf/202124712006 article EN cc-by EPJ Web of Conferences 2021-01-01
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