Douglas W. Marshall

ORCID: 0000-0002-3821-0025
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear and radioactivity studies
  • Nuclear Materials and Properties
  • Graphite, nuclear technology, radiation studies
  • Heat transfer and supercritical fluids
  • Granular flow and fluidized beds
  • Cyclone Separators and Fluid Dynamics
  • Geothermal Energy Systems and Applications
  • Thermal properties of materials
  • Iron and Steelmaking Processes
  • Nuclear Engineering Thermal-Hydraulics
  • Minerals Flotation and Separation Techniques
  • Rocket and propulsion systems research
  • Mining and Gasification Technologies
  • Mining Techniques and Economics
  • Magnetic Properties of Alloys
  • Anaerobic Digestion and Biogas Production
  • Heat Transfer and Boiling Studies
  • Decision-Making and Behavioral Economics
  • Stellar, planetary, and galactic studies
  • Pickering emulsions and particle stabilization
  • Fusion materials and technologies
  • Numerical methods in inverse problems
  • Catalytic Processes in Materials Science
  • Extraction and Separation Processes

Idaho National Laboratory
2014-2023

Torbay Hospital
2021

Torque (United States)
2021

Battelle
2008-2017

The next generation nuclear plant (NGNP)/advanced gas reactor (AGR) fuel development and qualification program includes a series of irradiation experiments in Idaho National Laboratory’s advanced test reactor. Tristructural isotropic (TRISO)-coated particles for the first AGR experiment, AGR-1, were produced at Oak Ridge Laboratory (ORNL) 2-in.(5-cm)-diameter coater. A requirement NGNP/AGR is to produce coated later coaters more representative industrial scale. Toward this end, tests have...

10.1115/1.3098424 article EN Journal of Engineering for Gas Turbines and Power 2009-06-10

As an important factor affecting the accuracy of thermal conductivity measurement, systematic (bias) error in guarded comparative axial heat flow (cut-bar) method was mostly neglected by previous researches. This bias is primarily due to mismatch between sample and meter bars (reference), which common for a unknown conductivity. A correction scheme, based on finite element simulation measurement system, proposed reduce magnitude overall uncertainty. scheme experimentally validated applying...

10.1088/0957-0233/25/5/055602 article EN Measurement Science and Technology 2014-03-14

The Next Generation Nuclear Plant (NGNP)/Advanced Gas Reactor (AGR) Fuel Development and Qualification Program includes a series of irradiation experiments in Idaho National Laboratory’s (INL’s) Advanced Test Reactor. TRISO-coated particles for the first AGR experiment, AGR-1, were produced at Oak Ridge Laboratory (ORNL) two-inch diameter coater. A requirement NGNP/AGR is to produce coated later coaters more representative industrial scale. Toward this end, tests have been performed by...

10.1115/htr2008-58074 article EN 2008-01-01

As part of the Department Energy’s Advanced Gas Reactor Fuel program, Babcock & Wilcox is developing a fluidized bed chemical vapor deposition process to deposit TRISO coating on UCO and UO2 kernels. These coated kernels will go into irradiation tests in Test at Idaho National Laboratory. This paper reports development activities including furnace design runs made qualify process.

10.1115/htr2008-58008 article EN 2008-01-01

The next generation nuclear power/advanced gas reactor (NGNP/AGR) fuel development and qualification program included the design, installation, testing of a 6-in. diameter particle coater to demonstrate quality tri-structural isotropic (TRISO) production on small industrial scale. Scale-up from laboratory-scale faced challenges associated with an increase in kernel charge mass, diameter, redesign distributor achieve adequate fluidization throughout deposition four TRISO coating layers....

10.1115/1.3126772 article EN Journal of Engineering for Gas Turbines and Power 2009-10-02

The Next Generation Nuclear Power/Advanced Gas Reactor (NGNP/AGR) Fuel Development and Qualification Program included the design, installation, testing of a 6-inch diameter nuclear fuel particle coater to demonstrate quality TRISO production on small industrial scale. Scale-up from laboratory-scale faced challenges associated with an increase in kernel charge mass, diameter, redesign gas distributor achieve adequate fluidization throughout deposition four coating layers. coatings are applied...

10.1115/htr2008-58073 article EN 2008-01-01
Coming Soon ...