Call Number (LC) | Title | Results |
---|---|---|
E 1.99:ornl-tm-228 | MEASUREMENT OF XENON POISONING IN THE HRT | 1 |
E 1.99:ornl-tm-229 | A FORTRAN PROGRAM FOR CALCULATING SINGLE CRYSTAL ABSORPTION CORRECTIONS | 1 |
E 1.99:ornl-tm-230 | SUPER-PROMPT-CRITICAL BEHAVIOR OF AN UNMODERATED UNREFLECTED URANIUM- MOLYBDENUM ALLOY ASSEMBLY | 1 |
E 1.99:ornl-tm-234 | A SYSTEM FOR GENERATING GAMMA RAY CROSS SECTION DATA FOR USE WITH THE IBM- 7090 COMPUTER | 1 |
E 1.99:ornl-tm-236 | Effective Cutoff Energies for B, Cd, Gd, and Sm Filters | 1 |
E 1.99:ornl-tm-237 | OGRE-P2, A MONTE CARLO PROGRAM FOR COMPUTING GAMMA-RAY LEAKAGE FROM LAMINATED SLABS WITH A DISTRIBUTED SOURCE | 1 |
E 1.99:ornl-tm-239 | EFFECT OF URANIUM-BEARING SCALE DEPOSITS ON HRE-2 CORE WALL TEMPERATURE, HEAT FLUX, AND PATCH TEMPERATURE | 1 |
E 1.99:ornl-tm-241 | THORIUM UTILIZATION PROGRAM A SURVEY OF PROCESSING METHODS FOR THORIUM REACTOR FUELS. | 1 |
E 1.99:ornl-tm-244 | WATER REQUIREMENTS FOR A RADIOCHEMICAL PROCESSING PLANT | 1 |
E 1.99:ornl-tm-249 | TESTS OF BEARING MATERIALS FOR THE EXPERIMENTAL THROUGH-TUBES IN THE EGCR | 1 |
E 1.99:ornl-tm-250 | IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY | 1 |
E 1.99:ornl-tm-251 | SAFETY CALCULATIONS FOR MSRE | 1 |
E 1.99:ornl-tm-252 | WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR FEBRUARY AND MARCH 1962 | 1 |
E 1.99:ornl-tm-255 | A PRODUCTION CONTROL METHOD FOR DETERMINING THE PARTICLE SIZE DISTRIBUTIONS OF THORIUM OXIDE AND THORIUM OXALATE | 1 |
E 1.99:ornl-tm-256 | CHEMICAL EFFECTS OF HIGH EXPLOSIVE SHOCK WAVES ON VARIOUS COMPOUNDS WHICH OCCUR IN THE GNOME CONTAINMENT MEDIUM | 1 |
E 1.99:ornl-tm-258 | A STUDY OF THE VISCOSITY OF THORIA SOLS | 1 |
E 1.99:ornl-tm-259 | THE CONTROL OF POT CALCINER TEMPERATURES TO ENSURE CALCINATION AT 900C | 1 |
E 1.99:ornl-tm-260 | HEAD-END TREATMENT OF LOW LEVEL WASTES PRIOR TO FOAM SEPARATION | 1 |
E 1.99:ornl-tm-263 |
Use of phosphite and hypophosphite to fix ruthenium from high-activity wastes in solid media THE USE OF PHOSPHITE AND HYPOPHOSPHITE TO FIX RUTHENIUM FROM HIGH-ACTIVITY WASTES IN SOLID MEDIA |
2 |
E 1.99:ornl-tm--264 | Critical mass studies. Part XII. Rover reactor fuel elements | 1 |