ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
ORNL-1771 - Oak Ridge National Laboratory
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7 .<br />
Mass Transfer in Liquid Lead ........................................... 100<br />
Flammability of Sodium Alloys .......................................... 102<br />
Thermodynamics of Alkali-Metal Hydroxides. ................................. 102<br />
Chemical Studies of Corrosion ............................................ 108<br />
Effect of Temperature on Corrosion of lnconel and Type 316 Stainless Steel ............. 108<br />
Corrosion by Fission Products .......................................... 109<br />
Controlled-Velocity Corrosion Testing Apparatus .............................. 109<br />
Reaction Between Graphite and Fluoride Melt ................................. 110<br />
Lithium Fluoride Castings ............................................. 110<br />
METALLURGY ..................................................... 111<br />
Stress-Rupture Tests of lnconel ........................................... 112<br />
High-Conductivity-Fin Sodium-to-Air Radiator ................................. 116<br />
Investigations of Fin Materials .......................................... 117<br />
Development of Brazing Alloys for Use in Fabricating Radiators .................... 118<br />
Radiator Fabrication ................................................. 120<br />
Nozzles for the Gas-Fired Liquid-Metal-Heater System ............................ 120<br />
Special Materials Fabrication Research., .................................... 121<br />
Stainless-Steel-Clad Molybdenum and Columbium. .............................. 121<br />
Inconel-Type Alloys ................................................. 122<br />
Nickel-Molybdenum-Base Alloys ......................................... 122<br />
Duplex Tubing. .................................................... 123<br />
Sigma-Phase Alloys ................................................. 124<br />
Boron Carbide Shielding ............................................... 124<br />
Tubular Fuel Elements ............................................... 124<br />
Metallographic Examination of a Fluoride-to-Sodium Heat Exchanger. .................. 124<br />
8 . HEAT TRANSFER AND PHYSICAL PROPERTIES ..............................<br />
Physical Properties Measurements .........................................<br />
Heat Capacity .....................................................<br />
Density and Viscosity ................................................<br />
Thermal Conductivity ................................................<br />
Electrical Conductivity ...............................................<br />
Vapor Pressure ....................................................<br />
Fused-Salt Heat Transfer. ..............................................<br />
Transient Boiling Research .............................................<br />
Fluid Flow Studies for Circulating-Fuel Reactors ...............................<br />
127<br />
127<br />
127<br />
127<br />
129<br />
129<br />
129<br />
130<br />
130<br />
131<br />
Heat Transfer Studies for Circulating-Fuel Reactors<br />
131<br />
.............................<br />
9 . RADIATIONDAMAGE ................................................. 134<br />
MTR Static Corrosion Tests ............................................. 134<br />
Fission Product Corrosion Study .......................................... 135<br />
Facilities for Handling Irradiated Capsules ................................... 135<br />
Analysis of Irradiated Fluoride Fuels for Uranium ............................... 136<br />
High-Temperature Check Valve Tests ....................................... 137<br />
Miniature In-Pile Loop - Bench Test ....................................... 137<br />
Life Tests on an RPM Meter. Bearings. and a Small Electric Motor Under Irradiation ......... 137<br />
Removal of Xenon from Fused Fluorides ..................................... 140<br />
C,F,.UF, Irradiation ................................................. 140<br />
LlTR Horizontal-Beam-Hole Fluoride-Fuel Loop ................................ 141<br />
<strong>ORNL</strong> Graphite Reactor Sodium-lnconel Loop .................................. 142<br />
Creep and Stress-Corrosion Tests ......................................... 142<br />
xi
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