Corrosion experiments with non-irradiated uranium-aluminium fuel elements were performed in MgCl2-rich brine. Distribution analysis of corroded material showed that about 90% of the initially available metallic U and Al precipitated. Investigations of these secondary corrosion products provided that one component is a Mg-Al-Cl-hydrotalcite. (C) 2003 Published by Elsevier B.V
On the basis of the political decision that there should be no reprocessing of spent research reacto...
As part of the U.S. National Spent Nuclear Fuel Program, aluminide fuels (UAl{sub x}) are being test...
Permanent disposal of spent nuclear fuel is proposed in a repository located in the volcanic tuff be...
The corrosion of the UAl-Al research reactorfuel type in synthetic MgCl2-rich brine (static batch-ty...
Corrosion experiments with non-irradiated U3Si2-Al research reactor fuel samples were carried out in...
For the assessment of a confident und sustainable final disposal of high level radioactive waste –fu...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium c...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Spent nuclear fuels from foreign and domestic research and test reactors being returned to SRS are n...
Storage of aluminum-clad spent nuclear fuel at the Savannah River Site (SRS) and other locations in ...
Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were f...
The discussion of a national fuel management concept for research reactor fuel elements is the reaso...
International audience300 series stainless steels are the most common materials used in the manufact...
In order to contribute to the long-term safety analysis of direct disposed research reactor fuel ele...
On the basis of the political decision that there should be no reprocessing of spent research reacto...
As part of the U.S. National Spent Nuclear Fuel Program, aluminide fuels (UAl{sub x}) are being test...
Permanent disposal of spent nuclear fuel is proposed in a repository located in the volcanic tuff be...
The corrosion of the UAl-Al research reactorfuel type in synthetic MgCl2-rich brine (static batch-ty...
Corrosion experiments with non-irradiated U3Si2-Al research reactor fuel samples were carried out in...
For the assessment of a confident und sustainable final disposal of high level radioactive waste –fu...
Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions ...
Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium c...
Introduction The Belgian Reactor 1 (BR1) fuel is composed of natural unalloyed metallic uranium, coa...
Spent nuclear fuels from foreign and domestic research and test reactors being returned to SRS are n...
Storage of aluminum-clad spent nuclear fuel at the Savannah River Site (SRS) and other locations in ...
Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were f...
The discussion of a national fuel management concept for research reactor fuel elements is the reaso...
International audience300 series stainless steels are the most common materials used in the manufact...
In order to contribute to the long-term safety analysis of direct disposed research reactor fuel ele...
On the basis of the political decision that there should be no reprocessing of spent research reacto...
As part of the U.S. National Spent Nuclear Fuel Program, aluminide fuels (UAl{sub x}) are being test...
Permanent disposal of spent nuclear fuel is proposed in a repository located in the volcanic tuff be...