Cliff Davis

ORCID: 0000-0003-3426-2773
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About
Contact & Profiles
Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Nuclear Engineering Thermal-Hydraulics
  • Heat transfer and supercritical fluids
  • Risk and Safety Analysis
  • Spacecraft and Cryogenic Technologies
  • Nuclear and radioactivity studies
  • Graphite, nuclear technology, radiation studies
  • Nuclear Physics and Applications
  • Fusion materials and technologies
  • Heat Transfer and Boiling Studies
  • Venous Thromboembolism Diagnosis and Management
  • Thermodynamic and Exergetic Analyses of Power and Cooling Systems
  • Hybrid Renewable Energy Systems
  • Radiative Heat Transfer Studies
  • Combustion and Detonation Processes
  • Acute Ischemic Stroke Management
  • Subcritical and Supercritical Water Processes
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Advanced Thermodynamic Systems and Engines
  • Peripheral Artery Disease Management
  • Chemical and Environmental Engineering Research
  • Tracheal and airway disorders
  • Cardiac Imaging and Diagnostics
  • Magnetic confinement fusion research

University of South Florida
2023

Tampa General Hospital
2023

Idaho National Laboratory
2003-2020

Massachusetts Institute of Technology
2002

University of Michigan
2002

Bechtel (United States)
2000

The Transient Reactor Test (TREAT) facility restarted transient operations in 2018 and has met or exceeded expectations for reactor experiments. TREAT's flexibility power shaping provides the ability to prescribe a variety of operating conditions test specimens, including shaped transients, steady-state irradiations, natural pulses, clipped deliver necessary energy deposition rate. initial following TREAT restart were designed mimic historical confirm capability. Then, studies performed...

10.1080/00295450.2018.1559712 article EN Nuclear Technology 2019-02-13

In this paper, a new neutron kinetics solver for cylindrical R-Z geometry, CYNOD, is presented the simulation of coupled transient problems pebble bed reactors. The code utilizes Direct Coarse Mesh Finite Difference method, in which set one-dimensional equations each transverse direction solved by means analytic Green’s function method. A method that deals with control rod cusping also presented. heterogeneous fuel kernel model implemented order to accurately take into account Doppler...

10.1115/htr2008-58255 article EN 2008-01-01

The U.S. Department of Energy and Idaho National Laboratory are developing a very high temperature reactor to serve as demonstration state-of-the-art nuclear technology. purpose the is twofold: (a) efficient, low-cost energy generation (b) hydrogen production. Although next-generation plant could be developed single-purpose facility, early designs expected dual purpose, assumed here. A dual-purpose design with combined cycle Brayton top bottom Rankine was investigated. An intermediate heat...

10.13182/nt06-a3769 article EN Nuclear Technology 2006-10-01

An air-cooled helical coil reactor cavity cooling system (RCCS) unit immersed in the water pool was proposed to overcome disadvantages of weak ability an RCCS and complex structure a water-cooled for high-temperature gas-cooled (HTGR). experimental apparatus constructed investigate various heat transfer phenomena pool-type RCCS, such as natural convection air inside cavity, radiation pool, forced pipe.The results were compared with published correlations. The CFX code validated using data...

10.13182/nt09-a8855 article EN Nuclear Technology 2009-07-01

A lead-bismuth–cooled fast reactor concept targeted for a balanced mission of actinide burning and low-cost electricity production is proposed its performance analyzed. The design explores the potential benefits thorium-based fuel in actinide-burning cores, particular terms reduction large reactivity swing enhancement small Doppler coefficient typical fertile-free burners. Reduced cost pursued through longer cycle length than that used burners thus higher capacity factor. It shown can...

10.13182/nt04-a3536 article EN Nuclear Technology 2004-09-01
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