Call Number (LC) Title Results
E 1.99:doe-id14204-f1 Novel Optimization Methodology for Welding Process/Consumable Integration 1
E 1.99:doe-id14207 Materials and Process Design for High-Temperature Carburizing Integrating Processing and Performance. 1
E 1.99:doe/id14257-1 Novel Carbon Films for Next Generation Rotating Equipment Applications 1
E 1.99:doe/id14261 High Selectivity Oxygen Delignification 1
E 1.99:doe id14548-1 Final Technical Report; NUCLEAR ENGINEERING RECRUITMENT EFFORT 1
E 1.99:doe-id14661-1 Detailed Reaction Kinetics for CFD Modeling of Nuclear Fuel Pellet Coating for High Temperature Gas-Cooled Reactors 1
E 1.99:doe/id14712-1 Verification of Allowable Stresses In ASME Section III Subsection NH For Grade 91 Steel & Alloy 800H 1
E 1.99:doe/id14712-2 Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV 1
E 1.99:doe/id14712-3 Improvement of ASME NH for Grade 91 1
E 1.99:doe/id14712-4 Updating of ASME Nuclear Code Case N-201 to Accommodate the Needs of Metallic Core Support Structures for High Temperature Gas Cooled Reactors Currently in Development 1
E 1.99:doe/id14712-5 Collect Available Creep-Fatigue Data and Study Existing Creep-Fatigue Evaluation Procedures for Grade 91 and Hastelloy XR 1
E 1.99:doe/id14712-6 A Review & Assessment of Current Operating Conditions Allowable Stresses in ASME Section III Subsection NH 1
E 1.99:doe/id14712-7 Review of Current Experience on Intermediate Heat Exchanger (IHX) and A Recommended Code Approach 1
E 1.99:doe/id14712-8 Creep and Creep-Fatigue Crack Growth at Structural Discontinuities and Welds 1
E 1.99:doe/id14712-9 Update and Improve Subsection NH - Simplified Elastic and Inelastic Design Analysis Methods 1
E 1.99:doe/id14712-10 Update and Improve Subsection NH –– Alternative Simplified Creep-Fatigue Design Methods 1
E 1.99:doe/id14712-11 New Materials for NGNP/Gen IV 1
E 1.99:doe/id14730-1 Design and Development of Selective Extractants for An/Ln Separations 1
E 1.99:doe/id14736 FEASIBILITY OF RECYCLING PLUTONIUM AND MINOR ACTINIDES IN LIGHT WATER REACTORS USING HYDRIDE FUEL 1
E 1.99:doe-id14742 The Development and Production of a Functionally Graded Composite for Pb-Bi Service 1