Call Number (LC) Title Results
E 1.99:ornl-2452 RADIATION EXCURSIONS AT THE ORNL CRITICAL EXPERIMENTS LABORATORY. I. MAY 26, 1954. II. FEBRUARY 1, 1956 1
E 1.99:ornl-2453 ANALYTICAL CHEMISTRY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING DECEMBER 31, 1957 1
E 1.99:ornl-2454 BREMSSTRAHLUNG SPECTRA IN NaI AND AIR 1
E 1.99:ornl-2456 A MODIFICATION OF THE SPHERICAL HARMONICS METHOD IN NEUTRON TRANSPORT THEORY 1
E 1.99:ornl-2457 THE ORNL THERMONUCLEAR PROGRAM 1
E 1.99:ornl-2460 HYDROFLUORIC ACID DECLADDING OF ZIRCONIUM-CLAD POWER REACTOR FUEL ELEMENTS 1
E 1.99:ornl-2461 DEVELOPMENT OF THE SULFEX PROCESS FOR DECLADDING STAINLESS-STEEL-CLAD POWER REACTOR FUEL ELEMENTS WITH SULFURIC ACID 1
E 1.99:ornl-2462 GAMMA-RAY DOSE RATES RESULTING FROM NEUTRON CAPTURES IN AIR 1
E 1.99:ornl-2464 ART REMOVAL AND DISASSEMBLY 1
E 1.99:ornl-2466 PROGRESS REPORT ON RAW MATERIALS FOR NOVEMBER 1957. Chemical Technology Div. 1
E 1.99:ornl-2467 THERMOCOUPLE RESEARCH REPORT FOR THE PERIOD NOVEMBER 1, 1956 TO OCTOBER 31, 1957. Progress Report No. 1 1
E 1.99:ornl-2468 CHEMICAL TECHNOLOGY DIVISION MONTHLY PROGRESS REPORT FOR DECEMBER 1957 1
E 1.99:ornl-2469 DEVELOPMENT OF THE EXCER PROCESS. III. PREPARATION OF URANIUM TETRAFLUORIDE FROM URANYL CHLORIDE BY IRON REDUCTION AND PRECIPITATION 1
E 1.99:ornl-2470 SAFEGUARD REPORT FOR A STAINLESS STEEL RESEARCH REACTOR FOR THE BSF (BSR- II) 1
E 1.99:ornl-2473 THOREX PROCESS THIRD URANIUM CYCLE STUDIES. 1
E 1.99:ornl-2474 MOLTEN-SALT REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JANUARY 31, 1958 1
E 1.99:ornl-2475 LABORATORY STUDIES ON THE GROUND DISPOSAL OF ORNL INTERMEDIATE-LEVEL LIQUID RADIOACTIVE WASTES 1
E 1.99:ornl-2476 SEGREGATION IN URANIUM-ALUMINUM ALLOYS AND ITS EFFECT ON THE FUEL LOADING OF ALUMINUM-BASE FUEL ELEMENTS 1
E 1.99:ornl-2477 A SUMMARY OF THE SEPARATION OPERATIONS 1
E 1.99:ornl-2478 OPERATIONAL SAFETY OF THE ORNL GRAPHITE REACTOR USING ENRICHED-URANIUM FUEL 1