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E 1.99:inl/con-10-20691
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Comparison of Nonlinear Model Results Using Modified Recorded and Synthetic Ground Motions |
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E 1.99:inl/con-10-20693
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The Need for Next Generation of Radiochemists in the USA |
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E 1.99:inl/con-10-20730
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Development of a propulsion system and component test facility for advanced radioisotope powered Mars Hopper platforms |
1 |
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E 1.99:inl/con-10-20731
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SCALE ANALYSIS OF CONVECTIVE MELTING WITH INTERNAL HEAT GENERATION |
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E 1.99:inl/con-10-20743
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Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-1 Experiment in the Advanced Test Reactor |
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E 1.99:inl/con-10-20745
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Development of an ICSBEP Benchmark Evaluation, Nearly 20 Years of Experience |
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E 1.99:inl/con-10-27602
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Development of Tritium Permeation Analysis Code (TPAC) |
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E 1.99:inl/con-11-20766
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Use of DRACS to Enhance HTGRs Passive Safety and Economy |
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E 1.99:inl/con-11-20775
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Benchmark Evaluation of the NRAD Reactor LEU Core Startup Measurements |
1 |
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E 1.99:inl/con-11-20780
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Creep-fatigue of High Temperature Materials for VHTR Effect of Cyclic Loading and Environment. |
1 |
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E 1.99:inl/con-11-20783
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A Second Look at Neutron Resonance Transmission Analysis as a Spent Fuel NDA Technique |
1 |
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E 1.99:inl/con-11-20790
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Sliding and Rocking of Unanchored Components and Structures Chapter 7.6 ASCE 4 Revision 2. |
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E 1.99:inl/con-11-20791
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Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory |
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E 1.99:inl/con-11-20811
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PRISMATIC CORE COUPLED TRANSIENT BENCHMARK |
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E 1.99:inl/con-11-20828
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Evaluation Metrics for Intermediate Heat Exchangers for Next Generation Nuclear Reactors |
1 |
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E 1.99:inl/con-11-20829
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Development of Figure of Merits (FOMs) for Intermediate Coolant Characterization and Selection |
1 |
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E 1.99:inl/con-11-20838
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GROWTH OF THE INTERNATIONAL CRITICALITY SAFETY AND REACTOR PHYSICS EXPERIMENT EVALUATION PROJECTS |
1 |
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E 1.99:inl/con-11-20849
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IMPACT OF ENERGY GROUP STRUCTURE ON NUCLEAR DATA TARGET ACCURACY REQUIREMENTS FOR ADVANCED REACTOR SYSTEMS |
1 |
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E 1.99:inl/con-11-20866
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Enhanced In-Pile Instrumentation at the Advanced Test Reactor |
1 |
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E 1.99:inl/con-11-20869
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DYNAMIC MODELING STRATEGY FOR FLOW REGIME TRANSITION IN GAS-LIQUID TWO-PHASE FLOWS |
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