E 1.99:ornl/tm--12656
|
A literature review of mixed waste components Sensitivities and effects upon solidification/stabilization in cement-based matrices. |
1 |
E 1.99:ornl/tm--12657
|
Evaluation of sulfur polymer cement as a waste form for the immobilization of low-level radioactive or mixed waste |
1 |
E 1.99:ornl/tm--12658
|
ITER ECH launcher options for start-up assist, bulk heating, and EC current drive experiments |
1 |
E 1.99:ornl/tm--12660
|
Fluid dynamic demonstrations for waste retrieval and treatment |
1 |
E 1.99:ornl/tm--12661
|
Nuclear medicine program progress report for quarter ending December 31, 1993 |
1 |
E 1.99:ornl/tm--12664
|
Thermodynamic property evaluation and magnetic refrigeration cycle analysis for gadolinium gallium garnet |
1 |
E 1.99:ornl/tm--12666
|
Modernization of the graphics post-processors of the Hamburg German Climate Computer Center Carbon Cycle Codes |
1 |
E 1.99:ornl/tm--12667
|
Validation of the scale system for PWR spent fuel isotopic composition analyses |
1 |
E 1.99:ornl/tm--12669
|
Using the log-normal distribution in analyzing aerosols The mathematical reasoning underlying the various diameters used and the plotting procedure. |
1 |
E 1.99:ornl/tm--12670
|
Evaluation of Torsatrons as reactors |
1 |
E 1.99:ornl/tm--12671
|
National Information Infrastructure Education Forum A summary report. |
1 |
E 1.99:ornl/tm--12672
|
Initial global 2-D shielding analysis for the Advanced Neutron Source core and reflector |
1 |
E 1.99:ornl/tm--12674
|
Ceramic Technology Project. Semiannual progress report for April 1993 through September 1993 |
1 |
E 1.99:ornl/tm--12675
|
The FALSTF last-flight computer program |
1 |
E 1.99:ornl/tm--12677
|
Evaluation of the need for emergency heat exchangers for long term emergency cooling of the Advanced Neutron Source Reactor |
1 |
E 1.99:ornl/tm--12679
|
Development and demonstration of treatment technologies for the processing of US Department of Energy Mixed Waste |
1 |
E 1.99:ornl/tm--12680
|
Netlib services and resources |
1 |
E 1.99: ornl/tm--12681
|
Primary system fission product release and transport A state-of-the-art report to the committee on the safety of nuclear installations. |
1 |
E 1.99:ornl/tm--12683
|
Regulatory facility guide for Ohio |
1 |
E 1.99:ornl/tm--12684
|
Regulatory Facility Guide for Tennessee |
1 |