A5079876130- Nuclear reactor physics and engineering
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Heat Transfer and Boiling Studies
- Graphite, nuclear technology, radiation studies
- Spacecraft and Cryogenic Technologies
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear Physics and Applications
- Magnetic confinement fusion research
- Nuclear and radioactivity studies
- Heat transfer and supercritical fluids
- Fluid Dynamics and Mixing
- Cyclone Separators and Fluid Dynamics
- Groundwater flow and contamination studies
- Rocket and propulsion systems research
- Molten salt chemistry and electrochemical processes
- Fluid Dynamics and Heat Transfer
- Heat Transfer and Numerical Methods
- Heat Transfer and Optimization
- Gas Dynamics and Kinetic Theory
- Thermodynamic and Structural Properties of Metals and Alloys
- Heat and Mass Transfer in Porous Media
- Nanopore and Nanochannel Transport Studies
- Offshore Engineering and Technologies
Oak Ridge National Laboratory
2011-2023
National Technical Information Service
2005
UT-Battelle
2005
Office of Scientific and Technical Information
1990-2005
Whitney Museum of American Art
2005
Pratt & Whitney (United States)
2005
United States Department of Energy
1992
Massachusetts Institute of Technology
1983
University of California, Berkeley
1975
AbstractThe use of a fusion component testing facility to study and establish, during the ITER era, remaining scientific technical knowledge needed by Demo is considered described in this paper. This aims test components an integrated nuclear environment, for first time, discover understand underpinning physical properties, develop improved further testing, time-efficient manner. It requires design with extensive modularization remote handling activated components, flexible hot-cell...
A study on the Fukushima Daiichi nuclear power station spent-fuel pool (SFP) at Unit 4 (SFP4) is presented in this paper. We discuss design characteristics of SFP4 and its decay heat load detail provide a model that we developed to estimate SFP evaporation rate based temperature. The level following March 11, 2011, accident predicted fundamental conservation laws mass energy. Our temperatures are good agreement with measured data consistent Tokyo Electric Power Company evaluation results.
The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious neutrons. This facility would be used to test, discover, and understand the complex challenges plasma material interactions, tritium fuel management, power extraction. Such properly designed provide, initially JET-level pressure (~30%T2) conditions (e.g., Hot-Ion H-Mode, Q<1)), an outboard neutron flux 0.25 MW/m2 while requiring...
IRIS is an advanced integral pressurized water reactor, developed by international consortium led Westinghouse. The licensing process requires the execution of and separate effect tests on a properly scaled reactor simulator for concept, safety system verification, code assessment. Within framework Italian R&D program Nuclear Fission, managed ENEA supported Ministry Economic Development, SPES3 facility under design will be built operated at SIET laboratories. simulates primary,...
A method for predicting steady state dispersed vertical upflow film boiling heat transfer under constant flux conditions is presented. Differential transport equations and accepted correlations are used to form a solution dependent upon knowledge of at the dryout point only. Thermal nonequilibrium included in analysis actual flow quality determined from local equilibrium conditions. nondimensional grouping derived which indicates extent present flow. Results this compared data three fluids...
The Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride salt–cooled High-temperature (FHR) that combines coated particle fuel and graphite moderator with liquid fluoride salt as coolant. DRACS features three coupled natural circulation/convection loops, relying completely on buoyancy driving force. These loops are through two exchangers, namely, exchanger (DHX) draft (NDHX). To experimentally investigate thermal performance of...