Reactor Development Program Progress ReportArgonne National Laboratory, 1963 - Nuclear energy |
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Page 1
... fuel assemblies , thereby providing the design force on the O - ring seals on the bottom of the fuel assemblies . Initial tests revealed an excessive leak rate . Most of this leakage was found to be caused by unsatisfactory welds at the ...
... fuel assemblies , thereby providing the design force on the O - ring seals on the bottom of the fuel assemblies . Initial tests revealed an excessive leak rate . Most of this leakage was found to be caused by unsatisfactory welds at the ...
Page 4
... fuel assembly concept was completed . This mockup will be used as a test section for air - flow pressure - drop measurements . b . Stainless Steel - clad Superheat Fuel . As mentioned in the April Progress Report ( ANL - 6717 , p . 3 ) ...
... fuel assembly concept was completed . This mockup will be used as a test section for air - flow pressure - drop measurements . b . Stainless Steel - clad Superheat Fuel . As mentioned in the April Progress Report ( ANL - 6717 , p . 3 ) ...
Page 58
... Fuel and Core Designs A reference mechanical design for the fuel and reactor - core struc- tures has been selected . Gap tolerances between fuel assemblies and core structural members are to be held to less than 0.015 in . It is ...
... Fuel and Core Designs A reference mechanical design for the fuel and reactor - core struc- tures has been selected . Gap tolerances between fuel assemblies and core structural members are to be held to less than 0.015 in . It is ...
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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