ORNL-1771 - Oak Ridge National Laboratory

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7 . Mass Transfer in Liquid Lead ........................................... 100 Flammability of Sodium Alloys .......................................... 102 Thermodynamics of Alkali-Metal Hydroxides. ................................. 102 Chemical Studies of Corrosion ............................................ 108 Effect of Temperature on Corrosion of lnconel and Type 316 Stainless Steel ............. 108 Corrosion by Fission Products .......................................... 109 Controlled-Velocity Corrosion Testing Apparatus .............................. 109 Reaction Between Graphite and Fluoride Melt ................................. 110 Lithium Fluoride Castings ............................................. 110 METALLURGY ..................................................... 111 Stress-Rupture Tests of lnconel ........................................... 112 High-Conductivity-Fin Sodium-to-Air Radiator ................................. 116 Investigations of Fin Materials .......................................... 117 Development of Brazing Alloys for Use in Fabricating Radiators .................... 118 Radiator Fabrication ................................................. 120 Nozzles for the Gas-Fired Liquid-Metal-Heater System ............................ 120 Special Materials Fabrication Research., .................................... 121 Stainless-Steel-Clad Molybdenum and Columbium. .............................. 121 Inconel-Type Alloys ................................................. 122 Nickel-Molybdenum-Base Alloys ......................................... 122 Duplex Tubing. .................................................... 123 Sigma-Phase Alloys ................................................. 124 Boron Carbide Shielding ............................................... 124 Tubular Fuel Elements ............................................... 124 Metallographic Examination of a Fluoride-to-Sodium Heat Exchanger. .................. 124 8 . HEAT TRANSFER AND PHYSICAL PROPERTIES .............................. Physical Properties Measurements ......................................... Heat Capacity ..................................................... Density and Viscosity ................................................ Thermal Conductivity ................................................ Electrical Conductivity ............................................... Vapor Pressure .................................................... Fused-Salt Heat Transfer. .............................................. Transient Boiling Research ............................................. Fluid Flow Studies for Circulating-Fuel Reactors ............................... 127 127 127 127 129 129 129 130 130 131 Heat Transfer Studies for Circulating-Fuel Reactors 131 ............................. 9 . RADIATIONDAMAGE ................................................. 134 MTR Static Corrosion Tests ............................................. 134 Fission Product Corrosion Study .......................................... 135 Facilities for Handling Irradiated Capsules ................................... 135 Analysis of Irradiated Fluoride Fuels for Uranium ............................... 136 High-Temperature Check Valve Tests ....................................... 137 Miniature In-Pile Loop - Bench Test ....................................... 137 Life Tests on an RPM Meter. Bearings. and a Small Electric Motor Under Irradiation ......... 137 Removal of Xenon from Fused Fluorides ..................................... 140 C,F,.UF, Irradiation ................................................. 140 LlTR Horizontal-Beam-Hole Fluoride-Fuel Loop ................................ 141 <strong>ORNL</strong> Graphite Reactor Sodium-lnconel Loop .................................. 142 Creep and Stress-Corrosion Tests ......................................... 142 xi
Remote Metallography ................................................ 144 Fission-Fragment Anneoling Studies ....................................... 145 High.Temperature. Short.Time.Grai n.Grewth Characteristics of lnconel ................. 145 BNL Neutron Spectrum - Radiation Damage Study .............................. 145 MTR Neutron-Flux Spectra - Radiation Damage Study ............................ 147 10 . ANALYTICAL STUDIES OF REACTOR MATERIALS., .......................... 148 Analytical Chemistry of Reactor Materials ................................... 148 Determination of Oxygen in Fluoride Fuels .................................. 148 Oxidation-Reduction Titrations in Fused Salts ............................... 150 Polarographic Studies in Fused Ammonium Formate ............................ 150 Conversion of UF, and UF, to the Respective Chlorides with BCI, .................. 151 Solubility of Tri- and Tetravalent Uranium Fluorides in Fused NaAICI4 ............... 151 Oxidation of UF, with Oxygen. ......................................... 152 Determination of Lithium. Potassium. Rubidium. and Fluoride Ion in NaF-KF(RbF)-LiF-Base Fuels.. ..................................... 152 Oil Contamination in ARE Helium ........................................ 154 Petrographic Investigations of Fluoride Fuels ................................. 154 Summary of Service Analyses ............................................ 154 PART Ill . SHIELDING RESEARCH 11 . SHIELDING ANALYSIS ............................................... 157 Slant Penetration of Composite Slab Shields by Gamma Rays ....................... 157 Air Scattering of Neutrons. ............................................. 158 Single Anisotropic Air Scattering in the Presence of the Ground (Shielded Detector) ....... 158 Single Isotropic Air Scattering in the Presence of the Ground (Unshielded Detector) ....... 158 Formulas for Multiple Scattering in a Uniform Medium ........................... 159 Ground Scattering of Neutrons ........................................... 162 Focusing of Radiation in a Cylindrical Crew Compartment. ........................ 163 12 . LIDTANKSHIELDING FACILITY. ....................................... 164 Reflector-Moderated Reactor and Shield Mockup Tests ........................... 164 Effective Removal Cross Section of Carbon .................................. 164 GE-ANP Helical Air Duct Experimentation. .................................. 166 13 . BULK SHIELDING FACILITY ........................................... 168 Reactor Radiations Through Slabs of Graphite ................................. 168 Reactor Air Glow ................................................... 170 Fuel Activation Method for Power Determination of the ARE 173 ....................... 14 . TOWER SHIELDING FACILITY .......................................... 175 Fast-Neutron Ground and Air Scattering Measurements ........................... 175 Calorimetric Reactor Power Deierrnination ................................... 175 GE-ANP R-1 Divided-Shield Mockup Tests ................................... 178 PART IV . APPENDIXES 15 . LIST OF REPORTS ISSUED DURING THE QUARTER ........................... 183 ORGANIZATION CHART OF THE AIRCRAFT NUCLEAR PROPULSION PROJECT .......... 185 xi i
Page 2 and 3: Contract No. W-7405-eng-26 AIRCRAFT
Page 4 and 5: 1. G. M. Adamson 2. R. G. Affel 3.
Page 6 and 7: 197-198. Powerplant Laboratory (WAD
Page 8: FOREWORD This quarterly progress re
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with and without 0.OZin.-thick cadm
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Part II MATERIALS RESEARCH
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132 ANP
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zirconium or aluminum complex, or l
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11. SHIELDING ANALYSIS J. E. Faulkn
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form in terms of the Spence functio
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these integral 5 become Let and the
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PERIOD ENDING SEPTEMBER IO, 7954 Al
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0 20 40 60 80 IO0 120 140 160 I, Di
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... Two configurations, a single du
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The thermal-neutron flux (Fig. 13.2
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E-7 1 O6 I 5 - - L I ___- 2 f o5 2
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TIME (rnin) PERIOD ENDING SEPTEMBER
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. - ., . ....._____... - PERiOD END
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PERIOD ENDING SEPTEMBER 10, 1954 Fi
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part IV APPENDIX
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REPORT NO. ~~-54-a-10 C F-54-6-4 CF
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