Nolan Goth

ORCID: 0000-0003-1971-572X
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About
Contact & Profiles
Research Areas
  • Nuclear reactor physics and engineering
  • Heat transfer and supercritical fluids
  • Nuclear Physics and Applications
  • Nuclear Materials and Properties
  • Fluid Dynamics and Turbulent Flows
  • Nuclear Engineering Thermal-Hydraulics
  • Fluid Dynamics and Vibration Analysis
  • Advanced Combustion Engine Technologies
  • Metallurgical Processes and Thermodynamics
  • Fusion materials and technologies
  • Molten salt chemistry and electrochemical processes
  • Particle accelerators and beam dynamics
  • Engineering Applied Research
  • Real-time simulation and control systems
  • Heat Transfer Mechanisms
  • Control Systems and Identification
  • Magnetic confinement fusion research
  • Radiative Heat Transfer Studies
  • Superconducting Materials and Applications
  • Spacecraft and Cryogenic Technologies
  • Vibration and Dynamic Analysis
  • Heat and Mass Transfer in Porous Media
  • Cold Fusion and Nuclear Reactions
  • Iron and Steelmaking Processes
  • Fault Detection and Control Systems

Oak Ridge National Laboratory
2022-2024

Texas A&M University
2016-2021

10.1016/j.ijheatfluidflow.2017.03.007 article EN publisher-specific-oa International Journal of Heat and Fluid Flow 2017-03-29

To achieve longer-life liquid-metal fast reactor cores, designers are considering to increase the wall gap of wire-wrapped hexagonal fuel bundles account for volumetric void swelling and radiation creep. A new test bundle has been constructed, with a larger than prior experiments, experimental pressure drop data have generated under laminar, transition, turbulent flow regimes (corresponding Re 250–19,000), complement existing database small bundles. The comparison set predictions four...

10.1115/1.4038086 article EN Journal of Fluids Engineering 2017-10-03

10.1016/j.ijheatmasstransfer.2021.120958 article EN publisher-specific-oa International Journal of Heat and Mass Transfer 2021-02-03

Abstract The Spallation Neutron Source at Oak Ridge National Laboratory operates the Cryogenic Moderator System (CMS) which provides hydrogen cooling 20K to three neutron moderators. Each loop is protected by multiple burst discs and reclosing relief valves. As a result of Proton Power Upgrade project, CMS moderator loops will hold more thus require piping modifications. Operational experience has demonstrated that transient pressure increases in these occasionally rupture discs. causes for...

10.1088/1757-899x/1301/1/012098 article EN IOP Conference Series Materials Science and Engineering 2024-05-01

Abstract Through support of the US Department Energy’s Office Basic Energy Sciences, Oak Ridge National Laboratory has begun applying machine learning methods to improve accelerator and target performance Spallation Neutron Source (SNS). These are being applied control optimization power upgrade SNS Cryogenic Moderator System (CMS). A numerical model CMS been developed study these optimizations system modifications using EcosimPro. This paper compares steady-state transient results with...

10.1088/1757-899x/1301/1/012088 article EN IOP Conference Series Materials Science and Engineering 2024-05-01

The Cryogenic Moderator System (CMS) is responsible for maintaining a steady flow of cold neutrons numerous physics experiments at the Spallation Neutron Source (SNS) in Oak Ridge National Laboratory (ORNL). Sudden losses beam power, known as trips, cause major disturbance to CMS due large step changes cooling demands. Ongoing efforts on upgrading neutron power from 1.4 2.0MW are expected generate larger transients that can further strain subsystems if they not properly controlled. To manage...

10.1016/j.ifacol.2023.10.1365 article EN IFAC-PapersOnLine 2023-01-01

This study recaps the experimental effort to characterize a transverse plane flow field in tightly-packed, 61-pin, wire-wrapped, hexagonal fuel bundle prototypical for sodium fast reactor. The motive was produce high spatiotemporal data computational fluid dynamics turbulence model validation. matched-index-of-refraction and laser-based optical measurement techniques were utilized on an isothermal facility. Measurements performed perpendicular axial flow. Fluid three types of subchannels...

10.1115/icone26-81462 article EN 2018-07-22

This study numerically investigated the effects of various contact strategies on thermal hydraulic behavior within a structured bed 100 explicitly modeled pebbles. Four and two conditions were considered. The to avoid singularities include decreasing pebble diameter, increasing bridging surfaces near region, capping region. One strategy, Strategy 3a, which involves with cylinder equal 10% was selected as baseline strategy because it addressed singularity while minimizing geometric changes...

10.3390/app14167343 article EN cc-by Applied Sciences 2024-08-20
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