| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:inl/ext-10-18190 | Summary of Conceptual Models and Data Needs to Support the INL Remote-Handled Low-Level Waste Disposal Facility Performance Assessment and Composite Analysis | 1 |
| E 1.99:inl/ext-10-18191 | Assessment of Potential Flood Events and Impacts at INL's Proposed Remote-Handled Low-Level Waste Disposal Facility Sites | 1 |
| E 1.99:inl/ext-10-18291 | Development of autonomous magnetometer rotorcraft for wide area assessment | 1 |
| E 1.99:inl/ext-10-18297 |
Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties Engineering Database of Liquid Salt Thermophysical |
2 |
| E 1.99:inl/ext-10-18317 | PARFUME User's Guide | 1 |
| E 1.99:inl/ext-10-18381 | NSTB Assessments Summary Report Common Industrial Control System Cyber Security Weaknesses. | 1 |
| E 1.99:inl/ext-10-18385 | Deep Well #4 Backup Power Systems Project Closeout Report | 1 |
| E 1.99:inl/ext-10-18420 | A REVIEW ON BIOMASS DENSIFICATION TECHNOLOGIE FOR ENERGY APPLICATION | 1 |
| E 1.99:inl/ext-10-18421 | RERTR-9 Summary Report | 1 |
| E 1.99:inl/ext-10-18456 | RERTR-10 Irradiation Summary Report | 1 |
| E 1.99:inl/ext-10-18459 | Review of Dissimilar Metal Welding for the NGNP Helical-Coil Steam Generator | 1 |
| E 1.99:inl/ext-10-18466 | Independent Verification and Validation SAPHIRE Version 8 Final Report Project Number N6423 U.S. Nuclear Regulatory Commission. | 1 |
| E 1.99:inl/ext-10-18533 | SPAR-H Step-by-Step Guidance | 1 |
| E 1.99:inl/ext-10-18610 | NGNP Fuel Qualification White Paper | 1 |
| E 1.99:inl/ext-10-18630 | INL Initial Input to the Mission Need for Advanced Post-Irradiation Examination Capability A Non-Major System Acquisition Project | 1 |
| E 1.99:inl/ext-10-18651 | Implementation of DOWTHERM A Properties into RELAP5-3D/ATHENA | 1 |
| E 1.99:inl/ext-10-18751 | Facility Safeguardability Analysis In Support of Safeguards-by-Design | 1 |
| E 1.99:inl/ext--10-18762-rev002 | Evaluation of Sedimentary Structure Near the Advanced Test Reactor Complex at the Idaho National Laboratory | 1 |
| E 1.99:inl/ext-10-18796 | Analysis of Reference Design for Nuclear-Assisted Hydrogen Production at 750°C Reactor Outlet Temperature | 1 |
| E 1.99:inl/ext-10-18845 | System Design Description and Requirements for Modeling the Off-Gas Systems for Fuel Recycling Facilities | 1 |
