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E 1.99:ucid-21362-vol.3
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Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers |
1 |
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E 1.99:ucid-21362-vol.5
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Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers |
1 |
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E 1.99:ucid-21362-vol.6
|
Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers |
1 |
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E 1.99:ucid-21362-vol.7
|
Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers |
1 |
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E 1.99:ucid-21362-vol.8
|
Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers |
1 |
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E 1.99:ucid-21386
|
Precise rotational alignment of x-ray transmission diffraction gratings |
1 |
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E 1.99:ucid-21390
|
Report of workshop on radiological effects of nuclear war, SCOPE-ENUWAR workshop, Moscow, USSR, March 21-25, 1988 |
1 |
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E 1.99:ucid-21394
|
Nonlinear dynamics of the electron self-field interaction |
1 |
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E 1.99:ucid-21400
|
Analysis of beryllium and depleted uranium An overview of detection methods in aerosols and soils. |
1 |
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E 1.99:ucid-21403
|
Bremsstrahlung from high Z impurities in hot plasmas |
1 |
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E 1.99:ucid-21404
|
Technology and physics in the Tokamak Program The need for an integrated, steady-state RandD tokamak experiment. |
1 |
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E 1.99:ucid-21411
|
Experiments in the application of ultrasound diffraction tomography for nondestructive testing |
1 |
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E 1.99:ucid--21414
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Thermal performance of a buried nuclear waste storage container storing a hybrid mix of PWR and BWR spent fuel rods |
1 |
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E 1.99:ucid--21414-rev.1
|
Thermal performance of a buried nuclear waste storage container storing a hybrid mix of PWR and BWR spent fuel rods; Revision 1 |
1 |
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E 1.99:ucid-21417
|
Solid state laser technology for inertial confinement fusion A collection of articles from ''Energy and Technology Review'' |
1 |
|
E 1.99:ucid-21429
|
Efficiency calculations for the direct energy conversion system of the Cadarache neutral beam injectors |
1 |
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E 1.99:ucid-21438
|
Structural evaluation of the Shippingport Reactor Pressure Vessel and Neutron Shield Tank package for impact and puncture loads |
1 |
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E 1.99:ucid--21444
|
Numerical modeling of the thermal and hydrological environment around a nuclear waste package using the equivalent continuum approximation Horizontal emplacement. |
1 |
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E 1.99:ucid-21453
|
The use of idle equipment for ITER (International Thermonuclear Engineering Reactor) magnet development |
1 |
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E 1.99:ucid-21459
|
PINEX (Pinhold Neutron Experiment) fluor characteristics |
1 |
