A|B|C|D|E|F|G|H|I|J|K|L|M|N|O|P|Q|R|S|T|U|V|W|X|Y|Z
A About the Program Abstract Book April 2003 Abstracts Recently Awarded ACR Hydrogen Production for Heavy Oil Recovery 2004-004-C Advanced Computational Thermal Fluid Physics (CTFP) and its Assessment for Light Water Reactors and Supercritical Reactors 2002-016-K Advanced Corrosion-Resistant Zr Alloys for High Burnup and Generation IV Applications 2003-020-K Advanced Dispersion Strengthened Ferritic Alloys and F/M Steels with Fine Nanoscale Dispersions 2008-002-F Advanced Multi-Physics Simulation Capability for Very High Temperature Gas-cooled Reactors (VHTRs) Alternative Methods for Treatment of TRISO Fuels 2004-006-K 2002 Annual Report 2003 Annual Report 2004 Annual Report 2005 Annual Report 2006 Annual Report 2007 Annual Report 2008 Annual Report Assessment of Existing Physics Experiments Relevant to VHTR Designs 2004-005-F Award Summary
B Bilateral Collaborations Brazil Bilateral Collaborations Brazil Collaboration FY05 Award List Brazil Collaboration FY06 Award List
C Canada Bilateral Collaborations Canada Collaboration FY04 Award List Canada Collaboration FY07 Award List Canada Collaboration FY08 Award List Comparison of Characterization Methods for Anisotropy and Microstructure of TRISO Particle Layers 2006-003-F Core Design Studies for Sodium-Cooled TRU Burner Reactors 2006-001-K
D Developing and Evaluating Candidate Materials for Generation IV Supercritical Water Reactors 2003-008-K Development and Characterization of New High-Level Waste Forms for Achieving Waste Minimization from Pyroprocessing 2007-004-K Development and Test of Cladding Materials for Lead-Alloy Cooled Transmutation Reactors 2004-005-K Development of Advanced Instrumentation and Control for an Integrated Primary System Reactor 2005-001-B Development of Advanced Suite of Deterministic Codes for VHTR Physics Analysis 2004-003-K Development of Advanced Voloxidation Process for Treatment of Spent Fuel 2007-002-K Development of Crosscutting Materials for the Electrochemical Reduction of Actinide Oxides Used in Advanced Fast Burner Reactors 2006-003-K Development of Computational Models for Pyrochemical Electrorefiners of Nuclear Waste Transmutation Systems 2007-006-K Development of Enhanced Reactor Operation Strategy through Improved Sensing and Control at Nuclear Power Plants 2002-020-K Development of Fuels for the Gas-Cooled Fast Reactor 2004-009-F Development of Generation IV Advanced Gas-Cooled Reactors with Hardened/Fast Neutron Spectrum 2001-002-F Development of Generation IV Advanced Gas-Cooled Reactors with Hardened/Fast Neutron Spectrum 2004-008-F Development of Head-end Pyrochemical Reduction Process for Advanced Oxide Fuels 2005-004-K Development of HyPEP, A Hydrogen Production Plant Efficiency Calculation Program 2005-002-K Development of Improved Models and Designs for Coated-Particle Gas Reactor Fuels 2001-003-F Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Power Reactors 2004-002-C Development of Materials for Supercritical Water-Cooled Reactor 2004-01-J Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor 2003-013-K Development of Structural Materials to Enable the Electrochemical Reduction of Spent Oxide Nuclear Fuel in a Molten Salt Electrolyte 2003-024-K Development of Technology for Viable International Deployment of Small Sodium-Cooled Fast Reactors 2007-005-K Development of Voloxidation Process for Treatment of LWR Spent Fuel 2004-004-K
E Enhanced Radiation Resistance through Interface Modification of Nano-Structured Steels for Gen IV In-Core Applications 2009-002-K Evaluation and Demonstration of Advanced Power Conversion and Hydrogen Generation Technologies for Low Emission Nuclear, Fossil and Renewable Energy Sources 2008-002-C Evaluation of Materials for Gas-Cooled Fast Reactors 2004-007-F Evaluation of Materials for Supercritical Water-Cooled Reactors 2004-003-C EU Bilateral Collaborations EU Collaboration FY04 Award List EU Collaboration FY06 Award List Experimental and Analytic Study on the Core Bypass Flow in a Very High Temperature Reactor 2008-002-K Experimental Investigation of Small Break LOCAs in Coupled Vessel/Containment Integral Reactors 2006-001-E Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents 2007-001-K
F France Bilateral Collaborations French Collaboration FY01 Award List French Collaboration FY02 Award List French Collaboration FY04 Award List French Collaboration FY06 Award List French Collaboration FY08 Award List Further Investigations of the Interface between SCWR and Cu-Cl Cycle, a Moderate Temperature Thermochemical Cycle 2007-002-C
G GFR Physics Experiments in the CEA-Cadarache MASURCA Facility 2004-006-F
H High Efficiency Hydrogen Production From Nuclear Energy: Laboratory Demonstration of S-I Water-Splitting 2002-001-F High-Temperature Electrolyzer Development 2004-001-C High-Temperature Nickel-Based Alloys for VHTR Applications: Mechanical and Corrosion Testing 2006-002-F Hydrogen Process High-Temperature Heat Source Coupling Technology 2004-001-F Hydrogen Production Using High Temperature Electrolysis 2007-001-C
I Improvement of the Decay Heat Removal System for VHTR(RCCS) 2005-003-K Investigation of Heat Transfer in Supercritical Fluids for Application to the Generation-IV Supercritical 2004-002-K
J Japan Bilateral Collaborations Japan Collaboration FY05 Award List Japan Collaboration FY06 Award List
K Korea (See Republic of Korea)
L Lower-Temperature Thermochemical Hydrogen Production 2004-007-C
M Management Melt Coolability and Concrete Interaction (MCCI) 2002-001-N
N Nano-Composited Steels for Nuclear Applications 2001-007-F New Abstracts Nuclear Data Uncertainty Analyses to Support Advanced Fuel Cycle Development 2008-003-K
O OECD Bilateral Collaborations OECD Collaboration FY02 Award List OSMOSE – An Experimental Program for Improving Neutronic Predictions of Advanced Nuclear Fuels 2004-002-F OSMOSE – An Experimental Program for Improving Neutronic Predictions of Advanced Nuclear Fuels 2001-006-F
P Participants List Passive Safety Optimization in Liquid Sodium-Cooled Reactors 2003-002-K Performance Evaluation of TRU-Bearing Metal Fuel for Sodium Fast Reactors to Achieve High Burnup Goal 2007-003-K PCAST Report PRA-Aided Design of Advanced Reactors with an Application to GFR Safety-Related Systems 2004-010-F Preliminary Assessment of Irradiation Performance of Zirconium Carbide (ZrC) TRISCO Fuel Particles Public Information Public Reports
R Republic of Korea Bilateral Collaborations Republic of Korea Collaborative FY02 Award List Republic of Korea Collaborative FY03 Award List Republic of Korea Collaboration FY04 Award List Republic of Korea Collaboration FY05 Award List Republic of Korea Collaboration FY06 Award List Republic of Korea Collaboration FY07 Award List Republic of Korea Collaboration FY08 Award List Republic of Korea Collaboration FY09 Award List Research Areas
S Screening of Gas-Cooled Reactor Termal-Hydraulics and Safety Analysis Tools and Experiment Data Base 2004-001-K Separation of Fission Products from Molten LiCl-KCl Salt Used for Electro-Refining of Metal Fuels 2006-002-K SiC/SiC Composites for Gen-IV Reactors 2008-001-F SiC/SiC for Control Rod Structures for Next Generation Nuclear Plants 2004-004-F Sodium-Cooled Fast Reactor Structural Design for High Temperatures and Long Core Lifetimes/Refueling Intervals 2007-007-K Study of Burning Transuranic Elements in Heavy and Light Water Reactors 2008-003-C Sulfur-Iodine Integrated Laboratory-Scale Experiment 2006-001-F Supercritical Carbon Dioxide Brayton Cycle Energy Conversion 2005-001-K Supercritical Water-Cooled Reactor Stability Analysis 2004-005-C System Implications of Multi-Modular Nuclear Power Plants 2006-001-B
T The Numerical Nuclear Reactor for High-Fidelity Integrated Simulation of Neutronic, Thermal-Hydraulic, and Thermo-Mechanical Phenomena 2002-010-K Thermal-Hydraulic Analyses and Experiments for GCR Safety 2004-003-F Thermal-Hydraulic Benchmark Studies for SCWR Safety 2004-006-C Thermochemical Hydrogen Production Process Analysis 2004-011-F
U Upgrading of the Athabasca Oil Sands for the Production of Diesel and Gasoline 2008-001-C
V VHTR Environmental and Irradiation Effects on High-Temperature Materials 2006-006-K
Z ZPPR-15 and BFS Critical Experiments Analysis for Generation of Physics Validation Database of Metallic-Fueled Fast Reactor Systems 2009-001-K
