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E 1.99:conf-900608-21
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Dynamic pressure approach to analysis of reactor fuel plate stability |
1 |
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E 1.99:conf-900608-22
|
Remote site survey and characterization for the National ER WM Program using the SRIP (Solider Robot Interface Project) vehicle |
1 |
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E 1.99:conf-900608-30
|
Balancing the roles for conservation, coal, nuclear, and other energy systems |
1 |
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E 1.99:conf-900608-32
|
International aspects of Oak Ridge National Laboratory |
1 |
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E 1.99:conf-900608-43
|
Thermal-hydraulic analysis of the HFIR (High Flux Isotope Reactor) |
1 |
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E 1.99: conf-900608--44
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TRAC (Transient Reactor Analysis Code) analyses of Savannah River 1985 L-Area test series |
1 |
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E 1.99: conf-900608--45
|
The effective diffusion coefficient for porous rubble |
1 |
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E 1.99: conf-900608--47
|
Diffusive release of radionuclides into saturated and unsaturated tuff |
1 |
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E 1.99: conf-900608--48
|
Release rates of radionuclides into dripping ground water |
1 |
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E 1.99:conf-900608-51
|
An application of oscillation damped motion for suspended payloads to the advanced integrated maintenance system |
1 |
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E 1.99:conf-900608-54
|
HVAC fault tree analysis for WIPP integrated risk assessment |
1 |
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E 1.99: conf-900608--57
|
A simple multiplicative model for computing azimuthal power variations in Savannah River Site reactor assemblies |
2 |
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E 1.99: conf-900608--58
|
Thermal hydraulics of steam generator sludge |
1 |
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E 1.99: conf-900608--absts
|
Fusion energy |
1 |
|
E 1.99: conf-900613--1
|
Fast Flux Test Facility core restraint system performance |
1 |
|
E 1.99: conf-900615--2
|
Evaluating thermographic phosphors in an operating turbine engine |
1 |
|
E 1.99:conf-900617-1
|
Flow-induced vibration of component cooling water heat exchangers |
1 |
|
E 1.99:conf-900617-2
|
Analytical simulation of seismic testing of VKL (Versuchskreislauf) piping system at the HDR (Heissdampfreaktor) Test Facility |
1 |
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E 1.99: conf-900617--4
|
Dynamic effect of sodium-water reaction in fast flux test facility power addition sodium pipes |
1 |
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E 1.99: conf-900617--5
|
Assessment of thermal fatigue crack propagation in safety injection PWR lines |
1 |
