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E 1.99:ornl/tm-7589
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Development of depletion perturbation theory for a reactor nodal code |
1 |
|
E 1.99:ornl/tm-7591
|
Tearing mode stability of tokamak plasmas with elliptical cross section |
1 |
|
E 1.99:ornl/tm-7597
|
Expected environments for a defense high-level waste repository in salt |
1 |
|
E 1.99:ornl/tm-7599
|
Accumulation of uranium, cesium, and radium by microbial cells bench-scale studies. |
1 |
|
E 1.99:ornl/tm-7602
|
Supplementary neutron flux calculations for the ORNL pool critical assembly pressure vessel facility |
1 |
|
E 1.99:ornl/tm-7604
|
Location of test bundle instrumentation and anticipated experimental values for the CFTL AG-1 bundle |
1 |
|
E 1.99:ornl/tm-7605
|
Nuclear medicine technology progress report for quarter ending September 30, 1980 |
1 |
|
E 1.99:ornl/tm-7607
|
Fabrication of high-uranium-loaded U₃O₈-Al developmental fuel plates |
1 |
|
E 1.99:ornl/tm-7608
|
Microcomputer-controlled remote pipetter design and evaluation of a prototype system. |
1 |
|
E 1.99:ornl/tm-7611
|
Neoclassical current effects in neutral beam-heated tokamaks |
1 |
|
E 1.99:ornl/tm-7615
|
Sixth personnel dosimetry intercomparison study |
1 |
|
E 1.99:ornl/tm-7616
|
Variational moment solutions to the Grad-Shafranov equation |
1 |
|
E 1.99:ornl/tm--7617
|
ORNL breeder reactor safety quarterly technical progress report, July-September 1980 |
1 |
|
E 1.99:ornl/tm-7618
|
Metallographic study of type 304 stainless steel long-term creep-rupture specimen. [595/sup 0/C] |
1 |
|
E 1.99:ornl/tm-7619
|
Catalog of computer simulated TEM images of small FCC and BCC dislocation loops |
1 |
|
E 1.99:ornl/tm-7621
|
Report of the Task Group Calculations to ICRP Committee 2, October 14-17, 1980 |
1 |
|
E 1.99:ornl/tm-7628
|
Design of fluidized-bed, biological denitrification systems |
1 |
|
E 1.99:ornl/tm-7629
|
Roofing research a bibliography. |
1 |
|
E 1.99:ornl/tm-7631
|
Method for sampling from fission neutron energy spectra. [For DEC KA-10] |
1 |
|
E 1.99:ornl/tm-7632
|
HTGR Base Technology Program. Task 2 concrete properties in nuclear environment. A review of concrete material systems for application to prestressed concrete pressure vessels. |
1 |
