Call Number (LC) Title Results
E 1.99:cf-50-7-86 A COMPARISON OF DESIGN NEUTRON FLUXES AND HEAT PRODUCTION 1
E 1.99:cf-50-7-160 ORNL SLUG PROBLEM--CAUSES AND PREVENTION. (thesis). Terminal Report for Period September 1948 to July 1950 1
E 1.99:cf-50-7-173 HRE HEAT BALANCE 1
E 1.99:cf-50-8-65 ANTIMONIAL LEAD AS A POSSIBLE GAMMA SHIELD 1
E 1.99:cf-50-8-98 SHIELDING OF NUCLEAR REACTORS. LECTURE V. THE ECONOMICAL DISTRIBUTION OF GAMMA AND NEUTRON ATTENUATING MATERIAL IN A REACTOR SHIELD 1
E 1.99:cf-50-8-116 RESONANCE ABSORPTION BY Xe 1
E 1.99:cf-50-9-37 REVIEW OF ORNL HOMOGENEOUS REACTOR EXPERIMENT BY THE REACTOR SAFEGUARD COMMITTEE 1
E 1.99:cf-50-9-38 RESTARTING OF HRE SOUP PUMP-SAFETY CONSIDERATIONS 1
E 1.99:cf-50-9-118 COMPARISON OF GAMMA INTENSITIES IN LID TANK, 100% H$sub 2$O AND 99.4% H$sub 2$O-.6% BORON 1
E 1.99:cf-50-10-133 GAS GENERATION IN THE HRE PRESSURIZER SYSTEM 1
E 1.99:cf-50-10-145 GAS GENERATION AND RADIATION DAMAGE IN THE HRE SOUP CIRCULATING PUMP 1
E 1.99:cf-50-12-23 METALLURGICAL FACTORS AFFECTING THE DISSOLVING RATE OF 7.5% U-92.5% Al ALLOY 1
E 1.99:cf-50-12-40 EXTRUSION AND HOT PIERCING OF URANIUM 1
E 1.99:cf-50-12-86 SHIELDING REQUIREMENTS FOR THE PULSAFEEDER SOUP PUMP 1
E 1.99:cf-51-1-6 EFFECT OF FAST NEUTRON ABSORPTION BY $sub 8$O$sup 16$ IN THE BOILER WATER ON THE INDUCED ACTIVITY OF STEAM IN THE POWER CIRCUIT OF THE HRE AT 1000 KW POWER LEVEL 1
E 1.99:cf-51-1-10 A REVIEW OF THE RELATIVE MERITS OF PACKED COLUMNS, PULSE COLUMNS, MIXER- SETTLER MECHANISMS, AND CENTRIFUGAL CONTRACTORS 1
E 1.99:cf-51-1-20 AN ANALYSIS OF A STEAM POWER CYCLE AS APPLIED TO A LARGE HOMOGENEOUS CIRCULATING FUEL REACTOR 1
E 1.99:cf-51-1-23 WELDING ALUMINUM BY THE ARGON-ARC TECHNIQUE 1
E 1.99:cf-51--4-152 Biweekly progress report April 16-30, 1951. 1
E 1.99:cf-51-4-155 URANIUM ORES RECOVERY PULSE COLUMN TESTS 1