E 1.99:dp-430
|
FABRICATION OF URANIUM OXIDE FUEL ELEMENTS |
1 |
E 1.99:dp-434
|
OXIDATION OF NEPTUNIUM(V) BY VANADIUM(V) |
1 |
E 1.99:dp-435
|
HEAVY WATER MODERATED POWER REACTORS. Progress Report for October 1959 |
1 |
E 1.99:dp-441
|
A VERSATILE RECORDING POTENTIOMETER |
1 |
E 1.99:dp-444
|
IMPROVED METHOD FOR PRECIPITATING MANGANESE DIOXIDE |
1 |
E 1.99:dp-445
|
HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT FOR NOVEMBER 1959 |
1 |
E 1.99:dp-446
|
A MONTE CARLO CODE FOR THE TRANSPORT OF NEUTRONS |
1 |
E 1.99:dp-447
|
ANION EXCHANGE RECOVERY OF PLUTONIUM FROM REDUCTION RESIDUES |
1 |
E 1.99:dp-450
|
A REMOTELY CONTROLLED METALLOGRAPH. PART II |
1 |
E 1.99:dp-452
|
MODERATOR TEMPERATURE COEFFICIENTS IN HEAVY WATER REACTORS |
1 |
E 1.99:dp--455
|
Heavy water moderated power reactors. Progress Report for December 1959 |
1 |
E 1.99:dp-459
|
HYDRAULIC CHARACTERISTICS OF A CONTINUOUS SOLVENT WASHER WITH CRITICALLY SAFE DIMENSIONS |
1 |
E 1.99:dp-461
|
A COLORIMETER FOR IN-LINE ANALYSIS OF URANIUM AND PLUTONIUM SOLUTIONS |
1 |
E 1.99:dp-463
|
THERMAL CONDUCTIVITY OF ALUMINUM-LITHIUM ALLOYS CONTAINING UP TO 8% LITHIUM |
1 |
E 1.99:dp-465
|
HEAVY WATER MODERATED POWER REACTORS. Progress Report for January 1960 |
1 |
E 1.99:dp-467
|
NEUTRON FLUX DISTRIBUTIONS IN NATURAL URANIUM TUBES (thesis) |
1 |
E 1.99:dp-469
|
A LEVEL INDICATOR FOR LIQUEFIED GASES |
1 |
E 1.99:dp-470
|
RECOVERY OF DEGRADED HEAVY WATER AT THE SAVANNAH RIVER PLANT |
1 |
E 1.99:dp-471
|
AUTOMATIC DOSE COMPUTER FOR RADIATION FILM BADGES |
1 |
E 1.99:dp-473
|
Sr$sup 90$ MONITORING AT THE SAVANNAH RIVER PLANT |
1 |