Call Number (LC) Title Results
E 1.99:geap--5702 ZIRCALOY-CLAD UO₂ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 4, August--October 1968. 1
E 1.99:geap--5705 SOUTHWEST EXPERIMENTAL FAST OXIDE REACTOR DEVELOPMENT PROGRAM. Eighteenth Quarterly Report, August--October 1968. 1
E 1.99:geap--5709 TWO-PHASE FLOW AND HEAT TRANSFER IN MULTIROD GEOMETRIES. Twelfth Quarterly Progress Report, July 1--September 30, 1968. 1
E 1.99:geap--5714 NOTCHED HIGH-STRAIN FATIGUE BEHAVIOR OF THREE LOW-STRENGTH STRUCTURAL STEELS. 1
E 1.99:geap--5715 FINAL FAST FLUX TEST FACILITY BACKUP DESIGN DEVELOPMENT REQUIREMENT REPORT. 1
E 1.99:geap--5716 REACTOR PRIMARY COOLANT SYSTEM RUPTURE STUDY. Quarterly Progress Report No. 14, July--September 1968. 1
E 1.99:geap--5719 SODIUM COMPONENTS DEVELOPMENT PROGRAM. MASS TRANSFER INVESTIGATIONS IN LIQUID METAL SYSTEMS. Quarterly Progress Report No. 7, September--November 1968. 1
E 1.99:geap--5720 A THERMODYNAMIC DATA PROGRAM INVOLVING PLUTONIA AND URANIA AT HIGH TEMPERATURES. Quarterly Report No. 5. 1
E 1.99:geap--5721 FFTF BACKUP DESIGN INTERFACE DEFINITION DISCUSSION OF SYSTEM REQUIREMENTS. 1
E 1.99:geap--5722 FINAL FAST FLUX TEST FACILITY BACKUP DESIGN SUMMARY REPORT. 1
E 1.99:geap--5724 BWR PRIMARY PIPING STRESSES FOR SYSTEM RELIABILITY ANALYSIS. 1
E 1.99:geap--5726 INFLUENCE OF STRESS/STRAIN CONCENTRATION AND MEAN STRESS ON THE LOW-CYCLE FATIGUE BEHAVIOR OF THREE STRUCTURAL STEELS AT ROOM TEMPERATURE. 1
E 1.99:geap--5739 TWO-PHASE FLOW AND HEAT TRANSFER IN MULTIROD GEOMETRIES. AIR--WATER FLOW STRUCTURE DATA FOR A ROUND TUBE, CONCENTRIC AND ECCENTRIC ANNULUS, AND NINE-ROD BUNDLE. 1
E 1.99:geap--5743 SPECIFIC ZIRCONIUM ALLOY DESIGN PROGRAM. Quarterly Progress Report Nos. 22 and 23. 1
E 1.99:geap--5744 ANALYTICAL PROCEDURES AND APPLICATIONS OF FLUENCE DETERMINATIONS FROM EBR- II FLUX WIRES. 1
E 1.99:geap--5746 ZIRCALOY-CLAD UO₂ FUEL ROD EVALUATION PROGRAM. Quarterly Progress Report No. 5, November 1968--January 1969. 1
E 1.99:geap--5748 HEAT TRANSFER COEFFICIENTS BETWEEN FUEL AND CLADDING IN OXIDE FUEL RODS. 1
E 1.99:geap--5753 SODIUM-COOLED REACTORS FAST CERAMIC REACTOR DEVELOPMENT PROGRAM. Quarterly Report No. 29, November 1968--January 1969. 1
E 1.99:geap--5754 SOUTHWEST EXPERIMENTAL FAST OXIDE REACTOR DEVELOPMENT PROGRAM. Nineteenth Quarterly Report, November 1968--January 1969. 1
E 1.99:geap--5769 RESEARCH AND DEVELOPMENT REQUIREMENTS FOR A 1000 MWe SODIUM-COOLED FAST REACTOR. TASK IV REPORT OF 1000 MWe LMFBR FOLLOW-ON WORK. 1