Reactor Development Program Progress ReportArgonne National Laboratory, 1963 - Nuclear energy |
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304 stainless steel alloy aluminum analysis annealing Argonne atoms axial BORAX-V burnup calculated capsule Central Drawers cesium iodide cladding surface completed containing core corrosion CP-5 fuel element crucible designed determine dew point diameter EBR-I electrical electrical breakdown energy equipment experiments exposure fabrication Figure fission fluidized fluorine flux foil fracture fuel assemblies fuel rods G values heat Hi-C hydrogen ignition temperatures indicated installed irradiated krypton material measurements metal mg/cm² Mn54 activity niobium Nuclear obtained operation oxidation oxygen percent plutonium plutonium hexafluoride Progress Report pump Radiation RDU/sec reaction reactor power removal Report for April resonance RUN NUMBER samples sintering sodium solubility specimens stainless steel stainless steel cladding steam Stress studies sulfide superheater superheater fuel Table tantalum tests Thermal Neutrons thermocouple transfer functions tubes tungsten Type 304 stainless U3Og uranium dioxide uranium dioxide pellets uranium hexafluoride w/o Fz alloy w/o Pu w/o Zr welding zirconium