E 1.99:conf-850996-4
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Nuclear power plant training simulator fidelity assessment |
1 |
E 1.99:conf-851007-1
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Verification of steady-state temperature predictions in an instrumented LMFBR driver subassembly |
1 |
E 1.99:conf-851007-2
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Conceptual design basis and temperature predictions in a simulated instrumented LMFBR blanket subassembly |
1 |
E 1.99: conf-851007-3
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Four-fluid model of PWR degraded cores |
1 |
E 1.99: conf-851007-4
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TRAC-PF1/MOD-1 analysis of Loss-Of-Flow Test L9-4 |
1 |
E 1.99: conf-851007-5
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Loss-of-flow transient characterization in carbide-fueled LMFBRs |
1 |
E 1.99: conf-851007-6
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Analysis of multiple-tube ruptures in both steam generators for the Three Mile Island-1 pressurized water reactor |
1 |
E 1.99:conf-851007-7
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Flow visualization study of inverted annular flow of post dryout heat transfer region. [PWR; BWR] |
1 |
E 1.99: conf-851007-8
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Los Alamos PWR feed-and-bleed studies summary results and conclusions |
1 |
E 1.99:conf-851007-11
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Two-phase gas bubble-liquid boundary layer flow along vertical and inclined surfaces |
1 |
E 1.99: conf-851007-12
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Considerations for realistic ECCS evaluation methodology for LWRs |
1 |
E 1.99: conf-851007-13
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Evaluation of BWR emergency procedure guidelines for BWR ATWS using RAMONA-3B code |
1 |
E 1.99:CONF-851007--13
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Behavior of dissolved molybdenum during localized corrosion of austenitic stainless steel |
1 |
E 1.99:conf-851007-14
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Steady state temperature profiles in two simulated liquid metal reactor fuel assemblies with identical design specifications |
1 |
E 1.99: conf-851007-15
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RAMONA-3B/MINET composite representation of BWR thermal-hydraulic systems |
1 |
E 1.99: conf-851007-16
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Containment building atmosphere response during severe accidents in high temperature gas-cooled reactors |
1 |
E 1.99: conf-851007-17
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Investigation of hydrogen stratification and its application for the assessment of containment failure modes for a BWR Mark III containment during core meltdown accidents |
1 |
E 1.99: conf-851009-1
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Further measurements of electron transmission and avalanche gain in narrow lead glass tubing |
1 |
E 1.99: conf-851009-2
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High range gamma radiation meter |
1 |
E 1.99: conf-851009-3
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Applications of a portable MCA in nuclear safeguards |
1 |