|
E 1.99:ornl-3186
|
PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II |
1 |
|
E 1.99:ornl-3187
|
TITANIUM PUMP LOOP FOR AQUEOUS SOLUTIONS AT HIGH TEMPERATURES |
1 |
|
E 1.99:ornl-3188
|
DESIGN REPORT FOR NMSR PRESSURIZED WATER LOOP AT ORR |
1 |
|
E 1.99:ornl-3189
|
HEALTH PHYSICS DIVISION ANNUAL PROGRESS REPORT, FOR PERIOD ENDING JULY 31, 1961 |
1 |
|
E 1.99:ornl-3191
|
INSTRUMENTATION AND CONTROLS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING JULY 1, 1961 |
1 |
|
E 1.99:ornl-3192
|
EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART II. CONVERSION TO SOLID BY POT CALCINATION |
1 |
|
E 1.99:ornl-3193
|
NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1961 |
1 |
|
E 1.99:ornl-3194
|
EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS |
1 |
|
E 1.99:ornl-3195
|
THE RELEASE OF Kr$sup 85$ FROM UO$sub 2$ IN ORR CAPSULES |
1 |
|
E 1.99:ornl-3197
|
RECORDING EQUIPMENT FOR INTERNAL FRICTION MEASUREMENTS |
1 |
|
E 1.99:ornl-3198
|
NIGHTMARE-AN IBM 7090 CODE FOR THE CALCULATION OF GAMMA HEATING IN CYLINDRICAL GEOMETRY |
1 |
|
E 1.99:ornl-3199
|
EQUIPOISE-3 A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER. |
1 |
|
E 1.99:ornl-3199(add.)
|
EQUIPOISE 3A |
1 |
|
E 1.99:ornl-3200
|
THE TWENTY GRAND PROGRAM FOR THE NUMERICAL SOLUTION OF FEW-GROUP NEUTRON DIFFUSION EQUATIONS IN TWO DIMENSIONS |
1 |
|
E 1.99:ornl--3201
|
BIOLOGY DIVISION SEMIANNUAL PROGRESS REPORT FOR PERIOD ENDING AUGUST 15, 1961 |
1 |
|
E 1.99:ornl-3202
|
STATUS REPORT NO. 2 ON CLINCH RIVER STUDY |
1 |
|
E 1.99:ornl-3203
|
PURIFICATION OF DEGRADED TRIBUTYL PHOSPHATE-HYDROCARBON DILUENT SOLUTIONS BY DISTILLATION STATUS SUMMARY. |
1 |
|
E 1.99:ornl-3204
|
RECOVERY OF STRONTIUM AND RARE EARTHS FROM PUREX WASTES BY SOLVENT EXTRACTION |
1 |
|
E 1.99:ornl-3205
|
NUMERICAL ANALYSIS OF NEUTRON RESONANCES |
1 |
|
E 1.99:ornl-3206
|
AN EVALUATION OF THE URANIUM CONTAMINATION ON THE SURFACES OF ALCLAD URANIUM-ALUMINUM ALLOY RESEARCH REACTOR FUEL PLATES |
1 |
