|
E 1.99:ornl-tm--4529
|
Effect of extended exposure to simulated LMFBR fuel reprocessing off-gas on radioiodine trapping performance of sorbents (final report) |
1 |
|
E 1.99:ornl-tm--4530
|
Calculations related to the application of silicon detectors in pion radiobiology |
1 |
|
E 1.99:ornl-tm--4533
|
Development of an axial-flow centrifugal gas bubble separator for use in MSR xenon removal system |
1 |
|
E 1.99:ornl-tm--4538
|
Gamma-ray production due to neutron interactions with fluorine and lithium for incident neutron energies between 0.55 and 20 MeV tabulated differential cross sections. |
1 |
|
E 1.99:ornl-tm--4539
|
Release of fission products from pyrocarbon-coated HTGR fuel particles during postirradiation anneals |
1 |
|
E 1.99:ornl-tm--4541
|
Effect of high helium content on stainless steel swelling |
1 |
|
E 1.99:ornl-tm--4542
|
Temperature of loose coated particles in irradiation tests |
1 |
|
E 1.99:ornl-tm--4544
|
Gamma-ray production due to neutron interactions with magnesium for incident neutron energies between 0.8 and 20 MeV tabulated differential cross sections. |
1 |
|
E 1.99:ornl-tm--4547
|
Unfolding spatial images from a position-sensitive proportional neutron counter |
1 |
|
E 1.99:ornl-tm--4550
|
Critical experiments and the 2200 m/sec neutron parameters |
1 |
|
E 1.99:ornl-tm--4551
|
Effects of neutron irradiation on loose and bonded inert particles coated with pyrolytic carbon and silicon carbide |
1 |
|
E 1.99:ornl-tm--4552
|
Corrosion of several iron- and nickel-base alloys in supercritical steam at 1000$sup 0$F |
1 |
|
E 1.99:ornl-tm--4554
|
Performance of candidate HTGR fuels in fuel rod irradiations in HFIR |
1 |
|
E 1.99:ornl-tm--4555
|
HETRAP a heat transfer analysis program. |
1 |
|
E 1.99:ornl-tm--4561
|
Plutonium--beryllium source safety testing program |
1 |
|
E 1.99:ornl-tm--4562
|
SUPERA, a display and analysis system for the VT-15 graphics display |
1 |
|
E 1.99:ornl-tm--4563
|
DSPSYS, an interactive display and analysis system for the VT-15 graphics display |
1 |
|
E 1.99:ornl-tm--4565
|
Measurement of the poloidal flux profile in a tokamak by utilizing neutral beam injection |
1 |
|
E 1.99:ornl-tm--4566
|
Tenth dosimetry intercomparison study, August 27--September 7, 1973 |
1 |
|
E 1.99:ornl-tm--4567
|
Assessment of coater size for the fuel refabrication prototype plant |
1 |
