A5079879493- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Heat Transfer Mechanisms
- Nuclear Engineering Thermal-Hydraulics
- Flow Measurement and Analysis
- Heat transfer and supercritical fluids
- Fluid Dynamics and Turbulent Flows
- Magnetic confinement fusion research
- Aerodynamics and Fluid Dynamics Research
Oak Ridge National Laboratory
2021-2024
Missouri University of Science and Technology
2019-2023
Sufficient cooling of plasma-facing materials remains an outstanding challenge in the design fusion reactor blankets commercial power demonstration plants. Due to its chemical inertness and low neutron interaction cross section, pressurized helium is a candidate coolant fluid for such systems; however, has small thermal mass compared liquid coolants, potentially reducing heat removal performance. To address this need, number transfer enhancements have been proposed improve efficiency...
A helium flow loop is being assembled at Oak Ridge National Laboratory to analyze heat transfer enhancement for systems such as blanket and divertor components. To efficiently identify optimum geometries in these applications, simulation work performed optimize test section designs that are built tested the operates 4 MPa a mass rate of 100 g/s. Different ribbed examine rib shape, height, orientation, spacing, three-dimensional orientation modeled simulated STAR-CCM+ compare their ability...
As the push for design and construction of a fusion pilot plant in U.S. continues, demand improved tools techniques that aid this process increases. Reliable rapid integrated simulations neutronics, heat transfer, fluid flow, other phenomena occurring reactors are necessary to efficient these complicated systems. Computational dynamic (CFD) can be computationally expensive part such simulations, 1-D "thermal hydraulic" models greatly reduce expense; use modeling frameworks as Multiphysics...
Sufficient cooling of the blanket first wall remains a critical challenge for design and deployment fusion power plants. Helium has been targeted as potential coolant due to its inertness low neutron interactivity, among other advantages. However, thermal mass helium creates need heat transfer enhancements in channels provide adequate blanket's wall. Toward this end, series ribbed flow various rib cross sections configurations produced via additive manufacturing (AM) study efficacy AM...
High-density graphitic foam is an ideal low-Z plasma-facing material for deuterium-deuterium plasma experiments where tritium codeposition not issue. However, like all carbon, suffers from a precipitous drop in thermal conductivity at high temperatures, >600°C. To mitigate these problems, functionally graded layers of tungsten can be deposited to thickness 2 4 mm onto the side using chemical vapor deposition. The then acts as high-conductivity heat sink temperatures below 600°C thin high-Z...
A densified graphite foam is being explored for its applicability as plasma-facing material in fusion devices. Three different monoblocks are constructed and tested the Garching Large Divertor Sample Testing Facility. The monoblock samples consist of press-fit to a single tube, cubes brazed single, tube. tube composed CuCrZr with steel twisted tape. exposed heat fluxes 5, 6, 8 MW/m <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sup> 30 s...
One technique for mitigating disruptions in a tokamak is shattered pellet injection (SPI). SPI process which large solid consisting of deuterium, neon, or argon desublimated pipe gun barsrel and launched downstream. Pellets are just before entering the plasma by an impact with angled tube. Injection these materials into radiates stored thermal energy, limits current decay rates, suppresses generation runaway electrons, dissipates electrons if necessary. A critical element system fast-acting...
Heat transfer enhancement geometries in rectangular channels are studied using computational fluids dynamics a large range of turbulent and heat conditions. Air-cooled possessing ribs on one or more sides with sided heating simulated STAR-CCM+ Reynolds-averaged Navier Stokes k-ω shear stress transport turbulence model under steady state Nusselt number ratio, friction factor, overall ratio used to evaluate compare the performance various rib designs. Using Design Manager MO-SHERPA algorithm...