ORNL-1771 - Oak Ridge National Laboratory

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CONTENTS FOREWORD. ......................................................... vii SUMMARY ........................................................... 1 PART I . REACTOR THEORY. COMPONENT DESIGN AND TESTING. AND CONSTRUCTION 1 . ClRCULATING-FUEL AIRCRAFT REACTOR EXPERIMENT ....................... 9 The Experimental Reactor System ......................................... Characteristics of the Fuel and the Sodium Systems During the Water Tests .............. Preparations for Loading the ARE ......................................... 11 3 . Fuel-Concentrate Injection Nozzle ......................................... 12 ARE Unloading Experiment .............................................. 12 ARE Fuel Recovery and Reprocessing ...................................... ARE Pumps ........................................................ Fabrication and Testing ............................................... Seal-Gas Pressure-Balancing System ...................................... Radiation Damage to Pump Drives ........................................ Radiation Damage to Shaft Seal .......................................... MotorTest ....................................................... Reactor System Component Test Loop. ...................................... Operation of Loop ................................................... Examination of Hairpin Tube ............................................ Reactor Physics. .................................................... 12 14 14 14 14 15 15 16 16 16 16 2 . REFLECTOR-MODERATED REACTOR ..................................... Design of the CFRE .................................................. CFRE Component Development Projects ..................................... Reactor Physics ..................................................... ReactorCalculations .................................................. Beryllium Thermal Stress Test ........................................... Beryllium-lnconel-Sodium Systems ......................................... Beryllium-Inconel-Sodium CompatibiIityTests ................................. Mass Transfer Tests in Thermal-Convection Loops ............................. Mass Transfer Tests in Forced-Circulation Loops .............................. 17 17 18 24 24 24 29 29 30 32 EXPERIMENTAL REACTOR ENGINEERING .................................. 34 In-Pile Loop Component Development ....................................... 34 Horizontal-Shaft Sump Pump ............................................ 34 Vertical-Shaft Centrifugal Sump Pump ...................................... 37 Hydraulic Motor Pump Drives ........................................... 38 Forced-Circulation Corrosion Loops ........................................ 38 Inconel Loops ..................................................... 38 Dissimilar Metal Loops ............................................... 41 Gas-Furnace Heat-Source Development ...................................... 41 Study of the Cavitation Phenomenon ........................................ 41 Expansion and Improvement of Thermal-Convection Loop Testing Facilities .............. 42 4 . CRITICAL EXPERIMENTS .............................................. 44 Reflector-Moderated Reactor ............................................. 44 Supercritical-Water Reactor .............................................. 47 9 10 ix
PART II . MATERIALS RESEARCH 5 . CHEMISTRYOF MOLTEN MATERIALS ..................................... 53 SolidPhaseStudies in the NaF.ZrF,.UF, System ............................... Visual Observation of Melting Temperatures in the NaF.UF, System ................... Phase Relationships in UF3-Bearing Systems .................................. UF, iin ZrF,. Bearing Systems ........................................... X UF, in NaF-KF-LiF Mixtures ........................................... UF, in NaF-RbF-LiF Mixtures .......................................... 58 UF, in the Individual Alkali-Metal Fluorides ................................. 58 UF, in Binary Alkali-Metal Fluoride Systems ................................ 60 Purification of Rubidium Fluorlde ......................................... 60 ........................................ Chemical Reactions in Molten Salts 60 Chemical Equilibria in Fused Salts ....................................... 60 Stability of Chroniium Compounds in Molten Fluorides .......................... 63 63 64 Preparation of Various Fluorides ......................................... 67 Fundamental Chemistry of Fused Salts ...................................... 67 EMF Measurements .................................................. 67 Solubility of Xenon in Molten Salts ........................................ 70 X-Ray Diffraction Studies in Salt Systems ................................... 70 Physical Chemistry .................................................. 72 Production of Purified Molten Fluorides ..................................... 72 72 73 77 78 Reduction of NiF, by H, in NaF.;ZrF, Systems ................................ Reduction of FeF, by H, in NaF.ZrF, Systems ............................... Use of Zirconium Metal as a Scavenging Agent ................................ Purification of NaF.ZrF, Mixtures by Electrolysis ............................. Preparation of UF,. Bearing Fuels ........................................ Alkali-Metal Fluoride Processing Facility ................................... Production Facility .................................................. 79 In-PileLoopLoading ................................................ 79 Chemistry of Alkali-Metal Hydroxides ....................................... 80 Purification., ..................................................... 80 Reaction of Sodium Hydroxide with Metals ................................... 86 6 . COaROSlONRESEARGH ............................................... 81 Static and Seesayv Corrosion Tests ......................................... 82 Brazing Alloys in NaF.ZrF,.UF, and in Sodium ............................... Special Stellite Heats in NaF.ZrF,.UF, and in Sodium ........................... ........................................... Hastelloy R in Various Media Inconel in Molten Rubidium ............................................. Carburization of Inconel by Sodium. ....................................... 89 Special Tar-Impregnated and Fired Graphite. ................................. 90 Ceramics in Various Media ........................................... 94 Fluoride Corrosion of lnconel in Thermal Convection I.-aops ........................ 95 Effect of UF, .in ZrF4-Base Fuels ........................................ 95 Effect of UF, in Alkali-Metal Base Fuels ................................... 96 Effect of Zirconium Hydride Additions to Fuel ................................ 98 Effect of Uranium Concentration ......................................... 98 Effect of lnconel Grain Size ............................................ 9% Fluoride Corrosion of Hastelloy B in Thermal-Convection Loops ..................... 98 Lithium in Type 316 Stainless Steel ........................................ 99 100 Fundamental Corrosion Research. ......................................... 54 55 56 57 57 82 83 85 86
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
Page 13 and 14: Remote Metallography ..............
Page 15 and 16: ANP QUARTERLY PROGRE.S.5 REPORT ver
Page 17 and 18: AMP QUARTERLY PROGRESS REPORT A dev
Page 20: part I REACTOR THEORY, COMPONENT DE
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Page 25 and 26: ANP QUARTERLY PROGRESS REPORT the A
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Page 42 and 43: Power level TABLE 2.6. COMPARISON O
Page 44 and 45: PERIOD ENDING SEPTEMBER JO, 1954 Fi
Page 46 and 47: I R j I Fig. 2.7. Surfaces of Beryl
Page 48 and 49: that will permit remote, momentary
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- 40 32 c 3 24 A F! P ._r >- k > ir
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with and without 0.OZin.-thick cadm
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Part II MATERIALS RESEARCH
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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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