E 1.99: conf-840650-1
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Improved accuracy general remapping algorithm |
1 |
E 1.99: conf-840650-3
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Numerical calculation of complex shock reflections in gases |
1 |
E 1.99: conf-840653-1
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New experimental techniques with the split Hopkinson pressure bar |
1 |
E 1.99: conf-840664-4
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Calculations of the reaction between uranium and water and comparison experimental observations |
1 |
E 1.99:conf-840664-5
|
Cation self-diffusion in Fe₂O₃ |
1 |
E 1.99:conf-840664-8
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Corrosion tests in Hawaiian geothermal fluids |
1 |
E 1.99: conf-840665-1
|
MSS generic model a beginning. |
1 |
E 1.99: conf-840676-1
|
Absorber coatings' degradation |
1 |
E 1.99: conf-840686-1
|
Response of a glass melter to steam explosion |
1 |
E 1.99:conf-840701-1-summ
|
Mechanistic prediction of iodine and cesium release from LWR fuel |
1 |
E 1.99:conf-840701-2
|
Fission product release and fuel cladding interaction in severe-accident tests of LWR fuel |
1 |
E 1.99: conf-840701-3
|
Release of volatile fission products from UO₂ |
1 |
E 1.99:conf-840701-5
|
Influence of radiation on formation of fission product aerosols during LWR degraded core accidents |
1 |
E 1.99:conf-840701-6
|
RAFT a computer model for formation and transport of fission product aerosols in LWR primary system. |
1 |
E 1.99:conf-840701-7
|
Transient fission gas release during direct electrical heating experiments |
1 |
E 1.99: conf-840701-9
|
Attenuation mechanisms in the transport of in-vessel radiological source term fission products in an LMFBR |
1 |
E 1.99:conf-840701-10
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TREAT light water reactor source term experiments program |
1 |
E 1.99:conf-840701-13
|
Mass spectrometric study of the release of volatile fission products from irradiated LWR fuel |
1 |
E 1.99:conf-840701-14
|
Fission product release from irradiated LWR fuel under accident conditions |
1 |
E 1.99:conf-840701-15
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TREAT light water reactor source term experiments program |
1 |