Danny Schappel

ORCID: 0000-0003-2673-4216
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About
Contact & Profiles
Research Areas
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Nuclear and radioactivity studies
  • Fusion materials and technologies
  • Graphite, nuclear technology, radiation studies
  • Advanced ceramic materials synthesis
  • Heat transfer and supercritical fluids
  • Nuclear materials and radiation effects
  • Hydrogen Storage and Materials
  • Nuclear Engineering Thermal-Hydraulics
  • Advanced materials and composites
  • Material Properties and Applications
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Silicon Carbide Semiconductor Technologies
  • Aluminum Alloys Composites Properties
  • Probabilistic and Robust Engineering Design
  • Metallurgy and Material Forming
  • Reservoir Engineering and Simulation Methods
  • Additive Manufacturing and 3D Printing Technologies
  • Aluminum Alloy Microstructure Properties
  • Silicon and Solar Cell Technologies

Oak Ridge National Laboratory
2019-2024

University of Tennessee at Knoxville
2018-2020

10.1016/j.jnucmat.2020.152335 article EN publisher-specific-oa Journal of Nuclear Materials 2020-06-30

10.1016/j.jnucmat.2019.151965 article EN publisher-specific-oa Journal of Nuclear Materials 2019-12-20

Abstract The high‐temperature oxidation of additively manufactured and chemically vapor infiltrated (3D‐printed SiC) has been compared to chemical deposited (CVD) SiC. 100‐h isothermal exposures were conducted at 1425° 1300°C 1 atm under both dry air steam environments. A SiC reaction tube was utilized reduce silica volatility. After 1300°C, on the 3D‐printed surface, which intrinsically rougher than CVD scales 70%–90% thicker convex regions concave/flat regions. In regions, large cracks...

10.1111/jace.17632 article EN publisher-specific-oa Journal of the American Ceramic Society 2020-12-28

This work introduces a meshed debonding model intended for use with tristructural isotropic (TRISO) fuel particles. The ability to better examine the potential effects of interface between coating layers will enable host investigations stress state when complex loading and interactions coated particles are taking place. In this work, is discussed in detail. Then, simulations presented show capabilities limitations model. First, traditional high-temperature gas reactor TRISO particle...

10.1080/00295639.2021.1955590 article EN Nuclear Science and Engineering 2021-08-25

This work presents a discussion on series of finite element analyses that assess stress evolution in the coating layers tristructural isotropic (TRISO) particles contact with each other while embedded matrix. The initial simulations were applied uniaxial pressure versus matrix elastic modulus. These predicted increasing silicon carbide TRISO decreasing second set focused effects heating and cooling associated dimensional change state layers. general finding was there no significant...

10.1080/00295639.2022.2090214 article EN Nuclear Science and Engineering 2022-08-05
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