Jason Hales

ORCID: 0000-0003-0836-0476
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About
Contact & Profiles
Research Areas
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Nuclear and radioactivity studies
  • Nuclear Engineering Thermal-Hydraulics
  • Fusion materials and technologies
  • Heat transfer and supercritical fluids
  • Graphite, nuclear technology, radiation studies
  • Advanced Combustion Engine Technologies
  • Radioactive element chemistry and processing
  • Probabilistic and Robust Engineering Design
  • Nuclear Physics and Applications
  • Combustion and Detonation Processes
  • Adhesion, Friction, and Surface Interactions
  • Contact Mechanics and Variational Inequalities
  • Dynamics and Control of Mechanical Systems
  • High Temperature Alloys and Creep
  • Composite Material Mechanics
  • Advanced Mathematical Modeling in Engineering
  • Cyclone Separators and Fluid Dynamics
  • Granular flow and fluidized beds
  • Distributed and Parallel Computing Systems
  • Superconducting Materials and Applications
  • Risk and Safety Analysis
  • Numerical methods in engineering
  • Manufacturing Process and Optimization

Idaho National Laboratory
2016-2025

ORCID
2023

University of Tennessee at Knoxville
2019

National Technical Information Service
2002-2010

Office of Scientific and Technical Information
2002-2010

Sandia National Laboratories
2004-2010

Halliburton (United Kingdom)
2006

Lawrence Livermore National Laboratory
2002

United States Department of Energy
2002

Association of Research Libraries
2002

The last 2 years have been a period of unprecedented growth for the MOOSE community and software itself. number monthly visitors to website has grown from just over 3,000 now averaging 5,000. In addition, 1,800 pull requests merged since beginning 2020, new discussions forum averaged 600 unique per month. previous publication cited 200 times it was published ago. This paper serves as an update on some key additions changes code ecosystem years, well recognizing contributions community.

10.1016/j.softx.2022.101202 article EN cc-by SoftwareX 2022-10-11

BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented Simulation Environment (MOOSE) finite element library. One of its major goals to have great amount flexibility in how it used, including types can analyze, geometry being modeled, modeling approach employed, and dimensionality size models. Fuel forms that be modeled include standard light water reactor fuel, emerging fuels, tri-structural isotropic particles, metallic fuels. platform for research...

10.1080/00295450.2020.1836940 article EN cc-by-nc-nd Nuclear Technology 2021-03-20

10.1016/j.jnucmat.2015.12.028 article EN publisher-specific-oa Journal of Nuclear Materials 2015-12-24

The description of intra-granular fission gas behaviour is a fundamental part any model for the prediction release and swelling in nuclear fuel. In this work we present describing evolution bubbles terms bubble number density average size, coupled to grain boundaries. considers processes single atom diffusion, nucleation, re-solution trapping at bubbles. derived from detailed cluster dynamics formulation, yet it consists only three differential equations its final form; hence, can be...

10.1016/j.jnucmat.2018.02.024 article EN cc-by Journal of Nuclear Materials 2018-02-17

10.1016/j.jnucmat.2021.152840 article EN publisher-specific-oa Journal of Nuclear Materials 2021-02-11
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