Reactor Development Program Progress ReportArgonne National Laboratory, 1962 - Nuclear energy |
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Contents
Elastic Scattering of Neutrons | 30 |
B Reactor Fuels and Materials Development | 36 |
Advanced Systems Research and Development | 51 |
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406 stainless steel AARR alloy aluminum Alundum argon axial blanket BORAX-V boric acid calculations calibration capsule cell chloride cladding completed control rods core cross section crucible density depleted uranium Development Program Progress EBR-II EBWR effect Elastic Scattering endotherms enriched uranium equipment experimental experiments facility filter fluidization fluorine flux foils fuel elements fuel pins fuel plates fuel-unloading machine heat transfer hexafluoride hydrogen hydrogen chloride ignition increase indicated inhours installed irradiated Kirn Counter liquid magnesium material measured melting metal natural tungsten neutron niobium nitrogen Nusselt Nusselt number obtained operation oxide oxygen particle pellets phase plug plutonium plutonium dioxide pressure Program Progress Report psig radial reaction Reactivity Coefficient Reactor Development Program reflector rhenium sample specimens subassemblies tantalum temperature tested thermal transfer function tubing two-zone UO₂ uranium dioxide uranium hexafluoride uranyl chloride vanadium volume percent worth zinc zirconium zone ZPR-III