Call Number (LC) Title Results
E 1.99:ornl/ltr--2015/82 On-Going International Research Program on Irradiated Concrete Conducted by DOE, EPRI and Japan Research Institutions. Roadmap, Achievements and Path Forward 1
E 1.99:ornl/ltr-2015/87 M3FT-15OR0202237 Submit Report on Results From Initial Coating Layer Development For UN TRISO Particles. 1
E 1.99:ornl/ltr--2015/91 Report on status of execution of SiC step document 1
E 1.99:ornl/ltr--2015/102 Radiation-Hardened Circuitry Using Mask-Programmable Analog Arrays. Report 3 1
E 1.99:ornl/ltr--2015/172 Fabrication of ATALANTE Dissolver Off-Gas Sorbent-Based Capture System 1
E 1.99:ornl/ltr--2015/189 M4FT-15OR03100421 Status Report on Alkaline Conditioning Studies. 1
E 1.99:ornl/ltr--2015/193 Post-Service Examination of PWR Baffle Bolts, Part I. Examination and Test Plan 1
E 1.99:ornl/ltr-2015/203 Analysis of Waste Isolation Pilot Plant Samples Integrated Summary Report. 1
E 1.99:ornl/ltr--2015/215 Final Report LiCaAIF<sub>6</sub> Eu Scintillator Family Neutron Detection. 1
E 1.99:ornl/ltr-2015/217 Severe Accident Test Station Activity Report 1
E 1.99:ornl/ltr--2015/258 Milestone Report - M3FT-15OR03120211 - Complete Iodine Loading of NO Aged Ag<sup>0</sup>-functionalized Aerogel 1
E 1.99:ornl/ltr--2015/289 Identification of Modeling Approaches To Support Common-Cause Failure Analysis 1
E 1.99:ornl/ltr--2015/343 Real-Time Wavelength Discrimination for Improved Neutron Discrimination in CLYC 1
E 1.99:ornl/ltr--2015/383 M3FT-15OR0202212 SUBMIT SUMMARY REPORT ON THERMODYNAMIC EXPERIMENT AND MODELING. 1
E 1.99:ornl/ltr--2015/407 RILEM TC ISR Summer 2015 Activity Report 1
E 1.99:ornl/ltr--2015/411 Fabrication of Natural Uranium UO<sub>2</sub> Disks (Phase II) Texas A&M Work for Others Summary Document. 1
E 1.99:ornl/ltr--2015/417 Steam Oxidation of FeCrAl and SiC in the Severe Accident Test Station (SATS) 1
E 1.99:ornl/ltr-2015/419 Making Quality HPGe Gamma Ray Spectrum Measurements for Uranium, the Role of FRAM for Analysis, Quality Control and Enrichment Measurements, and Opportunities for Improved Quantification Documentation 1
E 1.99:ornl/ltr--2015/423 Report detailing comparative analysis of results from high flux isotope reactor and national institute of standards technology small-angle neutron scattering experiments 1
E 1.99:ornl/ltr-2015/425 Evaluation of Tritium Content and Release from Pressurized Water Reactor Fuel Cladding 1