Call Number (LC) Title Results
E 1.99:cf-58-2-76 COMMENTS ON THE ANGLE OF REPOSE OF AQUEOUS ThO$sub 2$ SLURRIES 1
E 1.99:cf-58-2-77 RESUME OF INFORMATION ON HYDROGEN IN TITANIUM ALLOYS AND ITS IMPLICATIONS TO HRP 1
E 1.99:cf-58-2-109 PHASE I--FOREIGN REACTOR FUEL SAMPLE IRRADIATION. IRRADIATION REQUEST ORNL- MTR-35 1
E 1.99:cf-58-2-109(rev.) PHASE I--FOREIGN REACTOR FUEL SAMPLE IRRADIATION OF U-S$sub 1$-Al ALLOY. IRRADIATION REQUEST ORNL-MTR-35 1
E 1.99:cf-58-2-110 A PORTABLE BANDSAW FOR HOT CELL USE 1
E 1.99:cf-58-2-124 PROPOSAL FOR AN EXPERIMENTAL STUDY OF THERMAL GRADIENT MASS TRANSFER IN A THERMAL CONVECTION LOOP 1
E 1.99:cf-58-2-127 HIGH THERMAL-NEUTRON FLUX FROM FISSION OVER-SIMPLIFIED CASES 1
E 1.99:cf-58-2-135 DAREX PROCESS BATCH DISSOLUTION AND CHLORIDE REMOVAL STEPS FOR YANKEE ATOMIC FUEL. 1
E 1.99:cf-58-2-139 CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT, FEBRUARY 1958 1
E 1.99:cf-58-2-144 HRE-3 PRESSURIZER DESIGN 1
E 1.99:cf-58-3-8 HYDROCLONE PERFORMANCE IN THE SOLVENT RECOVERY SYSTEM OF THE THOREX PLANT 1
E 1.99:cf-58-3-27 FLUX-TRAP REACTOR WITH ABSORBER IN THE CENTER 1
E 1.99:cf-58-3-28 DECREASE IN HRE-3 BREEDING RATIO CAUSED BY ABSORPTIONS IN CORE TANK AND SHROUD 1
E 1.99:cf-58-3-55 NUCLEAR ENGINEERING LABORATORY WITH A POINT NEUTRON SOURCE 1
E 1.99:cf-58-3-67 PROPOSED DEVELOPMENT PROGRAM FOR TREATMENT OF RADIOACTIVE WASTES FROM MERCHANT SHIP REACTORS 1
E 1.99:cf-58-3-68 HOMOGENEOUS HIGH-FLUX REACTOR 1
E 1.99:cf-58-3-71 CHEMICAL TECHNOLOGY DIVISION UNIT OPERATIONS MONTHLY PROGRESS REPORT, MARCH 1958 1
E 1.99:cf-58-3-76 MAXIMUM THERMAL FLUX PER Mw IN THREE-REGION HOMOGENEOUS REACTORS 1
E 1.99:cf-58-3-85 ESTIMATE OF POTENTIAL FUEL REPROCESSING, REVISION NO. 22-PART A 1
E 1.99:cf-58-3-109 DISPERSION OF SOLUBLE RADIOACTIVE MATERIAL IN WATER 1