E 1.99:ornl-tm--4753
|
HTGR safety studies progress report for the period ending March 31, 1973 |
1 |
E 1.99:ornl-tm--4754
|
Shielding calculations for a 200-MeV proton accelerator and comparisons with experimental data |
1 |
E 1.99:ornl-tm--4757
|
Cost commentary on a proposed method for recovery of uranium from sea water |
1 |
E 1.99:ornl-tm--4759
|
Model to calculate mass flow rate and other quantities of two-phase flow in a pipe with a densitometer, a drag disk, and a turbine meter |
1 |
E 1.99:ornl-tm--4760
|
Initial assessment of the status of HTGR metallic structural materials technology |
1 |
E 1.99:ornl-tm--4762
|
Radiological assessment of radionuclides in liquid effluents of light water nuclear power stations |
1 |
E 1.99:ornl-tm--4763
|
Interim report on PCRV thermal cylinder axial tendon failures |
1 |
E 1.99:ornl-tm--4764
|
Second interim report on PCRV thermal cylinder axial tendon failures |
1 |
E 1.99:ornl-tm--4766
|
Spectrum of a linear antenna in a cold magnetized plasma |
1 |
E 1.99:ornl-tm--4768
|
Comparison of the potential radiological impact of recycle $sup 233$U HTGR fuel and LMFBR plutonium fuel released to the environment |
1 |
E 1.99:ornl-tm--4772
|
Plasma criteria for a low-impurity, circular tokamak |
1 |
E 1.99:ornl-tm--4774
|
Guide to General Atomic studies of hypothetical nuclear driven accidents for the Fort St. Vrain reactor |
1 |
E 1.99:ornl-tm--4775
|
Evaluation of T-111 forced-convection loop tested with lithium at 1370$sup 0$C |
1 |
E 1.99:ornl-tm--4777
|
Experimental Engineering Section semiannual progress report (excluding reactor programs), March 1, 1974--August 31, 1974 |
1 |
E 1.99:ornl-tm--4781
|
Example of the application of the CUEX methodology the calculated exposure resulting from routine stack releases from the Haddam Neck Nuclear Power Plant. |
1 |
E 1.99:ornl-tm--4786
|
1974 intercomparison of personnel dosimeters |
1 |
E 1.99:ornl-tm--4791
|
Operating instructions for the heavy-ion code HIC-1 |
1 |
E 1.99:ornl-tm--4800
|
Measurement of flaw size in a weld sample by ultrasonic frequency analysis |
1 |
E 1.99:ornl-tm--4802
|
Molten-salt reactor information system |
1 |
E 1.99:ornl-tm--4803
|
Calculated performance of a mineral--oil--iron ionization spectrometer |
1 |