E 1.99:inl/con-10-17954
|
CMMAD Usability Case Study in Support of Countermine and Hazard Sensing |
1 |
E 1.99:inl/con-10-17962
|
Modular Countermine Payload for Small Robots |
1 |
E 1.99:inl/con-10-17970
|
Automating Risk Assessments of Hazardous Material Shipments for Transportation Routes and Mode Selection |
1 |
E 1.99:inl/con-10-17975
|
Pressure Resistance Welding of High Temperature Metallic Materials |
1 |
E 1.99:inl/con-10-17985
|
Control Rod Malfunction at the NRAD Reactor |
1 |
E 1.99:inl/con-10-17987
|
Proposed SPAR Modeling Method for Quantifying Time Dependent Station Blackout Cut Sets |
1 |
E 1.99:inl/con-10-17996
|
Fission Product Monitoring and Release Data for the Advanced Gas Reactor -1 Experiment |
1 |
E 1.99:inl/con-10-18011
|
Evaluation Between Existing and Improved CCF Modeling Using the NRC SPAR Models |
1 |
E 1.99:inl/con-10-18012
|
Deterministic Modeling of the High Temperature Test Reactor with DRAGON-HEXPEDITE |
1 |
E 1.99:inl/con-10-18014
|
Thermo-Mechanical Analysis of Coated Particle Fuel Experiencing a Fast Control Rod Ejection Transient |
1 |
E 1.99:inl/con-10-18016
|
LARGE-SCALE HYDROGEN PRODUCTION FROM NUCLEAR ENERGY USING HIGH TEMPERATURE ELECTROLYSIS |
1 |
E 1.99:inl/con-10-18017
|
Development and Implementation of an Assay System for Rapid Screening of Transuranic Waste in Highly Contaminated Environments |
1 |
E 1.99:inl/con-10-18032
|
Completion of the first NGNP Advanced Gas Reactor Fuel Irradiation Experiment, AGR-1, in the Advanced Test Reactor |
1 |
E 1.99:inl/con-10-18033
|
The Next Generation Nuclear Plant Graphite Creep Experiment Irradiation in the Advanced Test Reactor |
1 |
E 1.99:inl/con-10-18035
|
Current Status of VHTR Technology Development |
1 |
E 1.99:inl/con-10-18043
|
Nodal Diffusion Burnable Poison Treatment for Prismatic Reactor Cores |
1 |
E 1.99:inl/con-10-18045
|
Investigation of Supercells for Preparation of Homogenized Cross Sections for Prismatic Deep Burn VHTR Calculations |
1 |
E 1.99:inl/con-10-18046
|
The Role of Environment of High Temperature Creep-Fatigue Behavior of Alloy 617 |
1 |
E 1.99:inl/con-10-18051
|
Fuel Accident Condition Simulator (FACS) Furnace for Post-Irradiation Heating Tests of VHTR Fuel Compacts |
1 |
E 1.99:inl/con-10-18053
|
Fast-Neutron Spectrometry Using a 3He Ionization Chamber and Digital Pulse Shape Analysis |
1 |