Advanced Research and Technology Development Fossil Energy Materials Program

1988 ◽  
Vol 110 (4) ◽  
pp. 670-676
Author(s):  
R. R. Judkins ◽  
R. A. Bradley
Keyword(s):  
Technology Development ◽  
National Laboratory ◽  
Development Program ◽  
Ceramic Composites ◽  
Department Of Energy ◽  
Energy Materials ◽  
Alloy Development ◽  
Fossil Energy ◽  
Oak Ridge ◽  
Research Activities

The Advanced Research and Technology Development (AR&TD) Fossil Energy Materials Program is a multifaceted materials research and development program sponsored by the Office of Fossil Energy of the U.S. Department of Energy. The program is administered by the Office of Technical Coordination. In 1979, the Office of Fossil Energy assigned responsibilities for this program to the DOE Oak Ridge Operations Office (ORO) as the lead field office and Oak Ridge National Laboratory (ORNL) as the lead national laboratory. Technical activities on the program are divided into three research thrust areas: structural ceramic composites, alloy development and mechanical properties, and corrosion and erosion of alloys. In addition, assessments and technology transfer are included in a fourth thrust area. This paper provides information on the structure of the program and summarizes some of the major research activities.

scholarly journals Erosion Research on the U.S. Department of Energy Fossil Energy Materials Program

1987 ◽  
Author(s):  
R. R. Judkins ◽  
R. A. Bradley
Keyword(s):  
Erosion Resistance ◽  
Energy Systems ◽  
Department Of Energy ◽  
Future Research ◽  
Energy Materials ◽  
Fossil Energy ◽  
Research Activities ◽  
Erosion Corrosion ◽  
Erosion Mechanisms ◽  
The U.S

Research projects on the U.S. Department of Energy Fossil Energy Materials Program are investigating the mechanisms of erosion and erosion-corrosion of alloys and cermets used in fossil energy systems. The aim is to obtain an understanding of erosion mechanisms that will provide the basis for the development or modification of alloys and cermets with improved erosion resistance. Projects on this program are outlined. Results of recent research activities are presented, and plans for future research are described.

Development of Testing Methodologies for Onsite Radioactive Material Storage Containers

2008 ◽  
Author(s):  
Matthew R. Feldman
Keyword(s):  
Lawrence Livermore National Laboratory ◽  
National Laboratory ◽  
Nuclear Material ◽  
Department Of Energy ◽  
Radioactive Material ◽  
Development Effort ◽  
Nuclear Facilities ◽  
Los Alamos National Laboratory ◽  
Oak Ridge ◽  
Transportation Technologies

Based on a recommendation from the Defense Nuclear Facilities Safety Board, the Department of Energy (DOE) Office of Nuclear Safety Policy and Assistance (HS-21) has recently issued DOE Manual 441.1-1 entitled Nuclear Material Packaging Manual. This manual provides guidance regarding the use of non-engineered storage media for all special nuclear material throughout the DOE complex. As part of this development effort, HS-21 has funded the Oak Ridge National Laboratory (ORNL) Transportation Technologies Group (TTG) to develop and demonstrate testing protocols for such onsite containers. ORNL TTG to date has performed preliminary tests of representative onsite containers from Lawrence Livermore National Laboratory and Los Alamos National Laboratory. This paper will describe the testing processes that have been developed.

PBMR Technology Development Projects at Stellenbosch University, South Africa

2008 ◽  
Author(s):  
R. T. Dobson
Keyword(s):  
Technology Development ◽  
Cooling System ◽  
Heat Engine ◽  
Organic Rankine Cycle ◽  
Development Program ◽  
Heat Pipes ◽  
Development Projects ◽  
Fuel Temperature ◽  
Two Phase ◽  
Research Activities

PBMR has initiated a research and development program wherein a network of expertise relating to PBMR-specific technology is to be established. As a result of this initiative four specific PBMR sponsored technology development projects have been initiated at Stellenbosch University. The work done and still to be done towards these projects will be presented. The first project relates to the characterization of the flow dynamics of particles (ions, atoms and clusters) in a high pressure and velocity (9 MPa and 120 m/s) stream of helium due to various body-force fields (magnetic, electric and centrifugal); the ultimate objective of this project is to develop a graphite dust and particle scrubbing system. The second project relates to an entirely passive reactor cooling system (RCCS) using thermosyphon-type heat pipes with no pumps and active controls. The third project relates to the fuel temperature measurement under normal and loss of coolant pressure conditions using a fibre-optic Bragg-grating method. A fourth project relates to energy efficiency improvement by the conversion of waste, decay, after and residual heat into electrical power. This project makes use of two-phase closed loop thermosyphon-type heat pipes to transport the heat to an external heat engine, such as free piston type Stirling engine or organic Rankine cycle system. The research activities needed to meet the objectives of the above projects will be presented and discussed in this paper.

Production function for short-rotation woody-crop Populus spp. plantations

1994 ◽  
Vol 24 (1) ◽  
pp. 180-184 ◽  
Author(s):  
David A. Lortz ◽  
David R. Betters ◽  
Lynn L. Wright
Keyword(s):  
Production Function ◽  
Cultural Practices ◽  
National Laboratory ◽  
Development Program ◽  
The United States ◽  
Oak Ridge ◽  
Short Rotation ◽  
Wide Range ◽  
Woody Crop ◽  
Populus Spp

Short-rotation woody-crop Populus spp. plantations have the potential to produce large amounts of biomass in short time periods, typically 4–8 years. A production function equation is shown to predict yields for such plantations. The equation is based, in part, on information from biomass production experiments conducted across the United States. These experimental plots are sponsored by the Biofuels Feedstock Development Program of Oak Ridge National Laboratory. The equation uses nine parameters including both cultural practices and climatic and soil site conditions as independent variables. The equation (R2 = 0.86) is accurate and applicable to a wide range of conditions.

scholarly journals Conceptual Design of a MEDE Treatment System for Sodium Bonded Fuel

2008 ◽  
Author(s):  
Carl E. Baily ◽  
Karen A. Moore ◽  
Collin J. Knight ◽  
Peter B. Wells ◽  
Paul J. Petersen ◽  
...  
Keyword(s):  
Spent Nuclear Fuel ◽  
National Laboratory ◽  
Department Of Energy ◽  
Test Facility ◽  
Evaporation Chamber ◽  
Oak Ridge ◽  
Uranium Fuel ◽  
Fuel Assemblies ◽  
Metal Fuel ◽  
Enriched Uranium

Unirradiated sodium bonded metal fuel and casting scrap material containing highly enriched uranium (HEU) is stored at the Materials and Fuels Complex (MFC) on the Idaho National Laboratory (INL). This material, which includes intact fuel assemblies and elements from the Fast Flux Test Facility (FFTF) and Experimental Breeder Reactor-II (EBR-II) reactors, as well as scrap material from the casting of these fuels, has no current use under the terminated reactor programs for both facilities. The Department of Energy (DOE), under the Sodium-Bonded Spent Nuclear Fuel Treatment Record of Decision (ROD), has determined that this material could be prepared and transferred to an off-site facility for processing and eventual fabrication of fuel for commercial nuclear reactors. A plan is being developed to prepare, package, and transfer this material to the DOE HEU Disposition Program Office (HDPO), located at the Y-12 National Security Complex in Oak Ridge, Tennessee. Disposition of the sodium bonded material will require separating the elemental sodium from the metallic uranium fuel. A sodium distillation process known as MEDE (Melt-Drain-Evaporate), will be used for the separation process. The casting scrap material needs to be sorted to remove any foreign material or fines that are not acceptable to the HDPO program. Once all elements have been cut and loaded into baskets, they are then loaded into an evaporation chamber as the first step in the MEDE process. The chamber will be sealed and the pressure reduced to approximately 200 mtorr. The chamber will then be heated as high as 650 °C, causing the sodium to melt and then vaporize. The vapor phase sodium will be driven into an outlet line where it is condensed and drained into a receiver vessel. Once the evaporation operation is complete, the system is de-energized and returned to atmospheric pressure. This paper describes the MEDE process as well as a general overview of the furnace systems, as necessary, to complete the MEDE process.

Sign in / Sign up

Export Citation Format

Share Document