|
E 1.99:ornl--4954
|
Small-angle scattering in stripping collisions of hydrogen atoms having energies of 1 to 10 keV in various gases |
1 |
|
E 1.99:ornl-4955
|
Evaluation for ENDF/B-IV of the neutron cross sections for ²³⁵U from 82 eV to 25 keV |
1 |
|
E 1.99:ornl--4956
|
Preparation, testing, and analysis of zinc diffusion samples, NASA Skylab Experiment M-558 |
1 |
|
E 1.99:ornl--4957
|
Numerical solution of ill-conditioned systems of linear equations |
1 |
|
E 1.99:ornl--4958
|
Power system EMP protection. Final report |
1 |
|
E 1.99:ornl--4960
|
Transient response of low frequency vertical antennas to high altitude nuclear electromagnetic pulse (EMP) |
1 |
|
E 1.99:ornl--4962
|
Development of cementitious grouts for the incorporation of radioactive wastes. Part I. Leach studies |
1 |
|
E 1.99:ornl--4965
|
Transuranium Processing Plant semiannual report of production, status, and plans for period ending December 31, 1973 |
1 |
|
E 1.99:ornl--4968
|
Planning guide for HTGR safety and safety-related research and development |
1 |
|
E 1.99:ornl--4969
|
Mathematical description of fission product transport in coated particles during postirradiation anneals |
1 |
|
E 1.99:ornl-4972
|
Morse Monte Carlo Radiation Transport Code System |
1 |
|
E 1.99:ornl-4972/r1
|
MORSE Monte Carlo radiation transport code system |
1 |
|
E 1.99:ornl-4972/r2
|
MORSE Monte Carlo radiation transport code system. [Sample problems] |
1 |
|
E 1.99:ornl-4975
|
Gas-Cooled Reactor Programs annual progress report for period ending December 31, 1973. [HTGR fuel reprocessing, fuel fabrication, fuel irradiation, core materials, and fission product distribution; GCFR fuel irradiation and steam generator modeling] |
1 |
|
E 1.99:ornl--4978
|
ORNL isotopic power fuels quarterly report for period ending March 31, 1974 |
1 |
|
E 1.99:ornl--4981
|
Tolerance factors for the two-parameter exponential distribution |
1 |
|
E 1.99:ornl--4984
|
Convergence of the discrete ordinates method for the transport equation |
1 |
|
E 1.99:ornl--4985
|
Gamma-ray production due to neutron interactions with $sup 68$Zn and the level structure of $sup 68$Zn |
1 |
|
E 1.99:ornl--4986
|
Technique for determining thermal and electrical conductivity and absolute Seebeck coefficient between 300 and 1000 K |
1 |
|
E 1.99:ornl--4987
|
Saturated pool and flow boiling studies with Freon-113 and water at atmospheric pressure |
1 |
