Call Number (LC) Title Results
E 1.99: naa-sr-memo--12184 METHODS FOR CALCULATING FAST-NEUTRON LEAKAGE FROM THE SNAP-TSF REACTOR AND PRELIMINARY RESULTS. 1
E 1.99:naa-sr-memo--12210 SNAP 8 experimental reactor fuel element behavior Atomics International task force review. 1
E 1.99:naa-sr-memo--12218 TEMPR 8 STEADY STATE THERMAL SIMULATION OF A SNAP REACTOR. 1
E 1.99:naa-sr-memo--12232 SCTI PRESSURE REDUCING VALVE BODY FAILURE. 1
E 1.99:naa-sr-memo--12268 REACTION OF RESIDUAL SODIUM IN HNPF PRIMARY SODIUM SYSTEMS. 1
E 1.99:naa-sr-memo--12282 FFTF VALVE EVALUATION. 1
E 1.99:naa-sr-memo--12295 S8DS VARIABLY SPACED CORE, EVALUATION, AND DESIGN. 1
E 1.99:naa-sr-memo--12324 THERMAL ANALYSIS OF DROP-CALORIMETER DETERMINATION OF SNAP FUEL SPECIFIC HEATS. 1
E 1.99:naa-sr-memo--12340(rev.) HALLAM NUCLEAR POWER FACILITY RETIREMENT PLAN. 1
E 1.99:naa-sr-memo--12347 COMPARISON OF BERYLLIUM PHOTONEUTRON DECAY SETS USING EXPERIMENTAL SNAP REACTOR DATA. 1
E 1.99:naa-sr-memo--12368 Electron microscopy analysis of irradiated S8ER and NAA 115-1 fuel 1
E 1.99:naa-sr-memo--12394 SODIUM PURITY REQUIREMENTS (A REVIEW AND EVALUATION). 1
E 1.99:naa-sr-memo--12420(vol.2) PIQUA NUCLEAR POWER FACILITY AVAILABILITY EVALUATION REPORT. VOLUME II. RELIABILITY BLOCK DIAGRAMS, MAJOR COMPONENT FAILURE DATA, FAILURE MODE AND EFFECT ANALYSES. 1
E 1.99:naa-sr-memo--12422 Atomics International contribution to 24th High Temperature Fuels Committee preliminary information 1
E 1.99:naa-sr-memo--12425 HYDROGEN PERMEATION THROUGH SNAP-8 FUEL ELEMENT CLADDING ASSEMBLIES. 1
E 1.99:naa-sr-memo--12467 NEUTRON AND GAMMA RAY ATTENUATION IN SODIUM SHIELDS. 1
E 1.99:naa-sr-memo--12582 LIQUID METAL LEVEL MEASUREMENT (SODIUM) STATE-OF-THE-ART-STUDY. 1
E 1.99:naa-sr-memo--12586 A DESIGN STUDY FOR FAST FLUX TEST FACILITY SECONDARY GAMMA SHIELD. 1
E 1.99: naa-sr-memo-part 1 SNAP 10A Environmental Test Status Report, February - March 1964 1
E 1.99:naa-sr-tdr-6778 Radiation damage study on the lithium hydride SNAP shield 1