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E 1.99:inl/ext-19-55892-rev000
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Select Transient Metallic Fuel Bison Benchmarks |
1 |
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E 1.99:inl/ext-19-55897-rev000
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Accident Tolerant Fuels Series 1 (ATF-1) Irradiation Testing FY 2019 Status Report |
1 |
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E 1.99:inl/ext-19-55900-rev000
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Status Report on Photothermal Radiometry Development |
1 |
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E 1.99:inl/ext-19-55902-rev000
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Demonstrate Thermal Property Measurement on Irradiated Fuel in IMCL |
1 |
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E 1.99:inl/ext-19-55918-rev000
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Diagnosis of Corrosion Process in Nuclear Power Plant Secondary Piping Structures |
1 |
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E 1.99:inl/ext-19-55958-rev000
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Summary of Grizzly Development for Advanced Reactor Structural Materials |
1 |
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E 1.99:inl/ext-19-55962-rev000
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Detailed Analysis of RUS Insertion Experiment and Scoping Studies for Performing Next Experiment using an Enriched Fuel Sample |
1 |
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E 1.99:inl/ext-19-55969-rev000
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Modeling and Simulation - Introducing hardware-in-the-loop capabilities to the Human Systems Simulation Laboratory |
1 |
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E 1.99:inl/ext-19-56000-rev000
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FY19 Report for Instrumentation Development for the Transient Testing Program |
1 |
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E 1.99:inl/ext-19-56006-rev000
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Second Annual Progress Report on Ultrasonic Sensors for TREAT Fuel Condition Measurement and Monitoring |
1 |
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E 1.99:inl/ext-19-56012-rev000
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Progress on Grizzly Development for Reactor Pressure Vessels and Reinforced Concrete Structures |
1 |
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E 1.99:inl/ext-19-56017-rev000
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Aluminum-clad Spent Nuclear Fuel Engineering Scale Drying Experiment Design |
1 |
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E 1.99:inl/ext-19-56019-rev000
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M3MS-19IN0101201 Modeling Intra-granular Fission Gas Bubble Evolution in Uranium Dioxide during Transients |
1 |
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E 1.99:inl/ext-19-56029-rev000
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Nuclear Fuel Cycle and Supply Chain (NFCSC). Technical Monthly, July FY-19 |
1 |
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E 1.99:INL/EXT-19-56132-Rev001
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U.S. Industry Opportunities for Advanced Nuclear Technology Development |
1 |
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E 1.99:inl/ext-19-56215-rev000
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Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model |
1 |
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E 1.99:inl/ext-19-56234-rev000
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Quarterly Management Document ? FY19, 4th Quarter, Physics-based Creep Simulations of Thick Section Welds in High Temperature and Pressure Applications |
1 |
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E 1.99:inl/ext-19-56239-rev000
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Post-Irradiation Examination (PIE) of Westinghouse-led ATF Concepts U3Si2 and U3Si2-UN. Rodlet Non-Destructive Examinations and Sectioning Diagram. |
1 |
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E 1.99:inl/ext-19-56291-rev000
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October 2019 SAPHIRE 8 Software Quality Assurance; Maintenance and General Support Status Report |
1 |
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E 1.99:inl/ext-19-56292-rev000
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October 2019 SAPHIRE 8 Software Quality Assurance Oversight Status Report |
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