ORNL-4191 - the Molten Salt Energy Technologies Web Site

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12 . SEPARtZTION OF FISSION PRODUCTS ANI) OF' PROTACTINIUM FROM MOLTEN FLUORIDES ..................................................................................................................... 12.1 Extraction of Protactinium from Molten Fluorides into Molten Metals .................................... 12.2 Stability of Protactinium-Bismuth Solutions Contained in Graphite ........................................ 12.3 Attempted Electrolytic Deposition of Protactinium ............................................................. 12.4 Protactinium Studies in the High-Alpha Molten-Salt Laboratory ................................................ Reduction of Iron Dissolved in Molten LiF-ThF, ............................. ................................... Thorium Reduction in the Presence of an Iron Surface (Biillo Process) ................................. Thorium Reduction Followed by Filtration ............................................................................... Conclusion ...................................................................................................................................... 12.5 12.6 vi MSBIi Fuel Reprocessing by Reductive Extraction into Molten Bismuth ................................ Reductive Extraction of Cerium from LiF-BeF, (66-31 Mole X) .into Pb-Bi . . Eutectic Mixture ........................................................................................................................... 13 . BEHAVIOR OF BF, AND FLUOROBORATE MIXTURES ..................................................................... 158 13.1 Phase Relations in Fluoroborate Systems ................................................................................. 158 13.2 Dissociation Vapor Pressures in the NaBF,- NaF System .......................................................... 159 13.3 Reactions of Fluoroborates with Chromium and Other Hastelloy N Constituents .................. 161 Apparent Mass Transfer of Nickel .................................................................................................. 163 13.4 Reaction of BF, with Chromium Metal at 650°C .................... .............................................. 163 13.5 Compatibility of BF', with Gulfspin-35 Pump Oil at 150°F ........................................................ 164 14 . DEVELOPMENT AND EVALUATION OF ANALYTICAL METHODS FOR MOLTEN-SALT REACTORS ...................................................................................................... 14.1 Determination of Oxide in MSRE Salts ............................................................ 14.2 Determination of U3' in Radioactive Fuel by a Hydrogen Reduction Method ....... 14.3 In-Line Test Facility .............................................. ....................................................... 14.4 Electroreduction of Uraniurn(1V) in Molten LilF-EeF,-ZrF, at Fast Scan Rates .. and Short Transition Times .......................................................................................................... 14.5 Spectrophotometric Studies of Molten Fluoride Salts ........................................ ............... 14.6 Analysis of Off-Gas from Compatibility Tests of MSRE Pump Oil with BF, .......................... 14.7 Development of a Gas Chromatograph for the MSKE Blanket Gas .......................................... PART 4 . MOLTEN-SALT IRRADIATION EXPERIMENTS 148 148 149 151 1.53 153 153 154 154 154 15 . MOL'1'EN-SALT CONVECTION LOOP IN THE ORR .............................................................................. 176 15.1 Loop Description ....... ................................................................................................................. 176 15.2 Operation ............................................................................................................................................ 177 15.3 Operating Temperatures ....... ..................................................................................... 179 15.4 Salt Circulation by Convection ..................................................................................................... 180 15.5 Nuclear Heat, Neutron Flux, and Salt Power Density ................................................................ 180 15.6 Corrosion .......................................................................................................................................... 181 156 166 167 167 169 169 171 172 172
. 15.7 Oxygen Analysis .............................................................................................................................. 15.8 Crack in the Core Outlet Pipe .................................. .................................................. 15-9 Cutup of Loop and Preparation of Samples .................................................................................. 15.10 Metallographic Examination ................................................................................................... 15.11 Isotope Activity Calculation from Flux and Inventory History .................................................. 15.12 Isotope Activity Balance ............................................................................ .............................. 15.13 Uranium-235 Observed in Graphite Samples ..................... ....................................................... 15.14 Penetration of Fission Products into Graphite and Deposition onto Surfaces ........................ vii 15.15 Gamma Irradiation of Fuel Salt in the Solid Phase ..................................................................... PART 5 . MATERIALS DEVELOPMENT 16 . MSRE SURVEILLANCE PROGRAM ..... ................................................................................................ 16.1 General Description of the Surveillance Facility and Observations on Samples Removed ....................................................................................... .............................. 16.2 Mechanical Properties of the MSRE Hastelloy N Surveillance Specimens .............................. 17 . GRAPI-IITE STUDIES .................................................................................... ................. 17.1 Mateiials Procurement and Property Evaluation ............................ 17.2 Graphite Surface Sealing with Metals ............................................................................................ 17.3 Gas Impregnation of MSBR Graphites ............................................ ......................... 17.4 Irradiation of Graphite ...................... .......................................................................... 18 . HASTELLOY N STUDIES .......................................................................................................................... 18.1 Imprcivitig the Resistance of Hastelloy N to Radiation Damage by Composition Modifications .......................... ............................................................................ 18.2 Aging Studies on Titanium-Modified Hastelloy N ........................................................................ 18.3 Phase Identification Studies in Hastelloy N ............ ............................................. 18.4 Hot-Ductility Studies of Zirconium-Rearing Modified Hastelloy N ........ ............................... 18.5 Residual Stress Measurements in Hastelloy N Welds .................................................................. 18.6 Corrosion Studies ...................................................... ........................................................... File 1 Salts ................................................................................................................ Coolmt Salts .................................................................................................................................... Equipment Modifications ............ .............................................................................. 18.7 Titanium Diffusion in Hastelloy N .......................................................... ............................... 18.8 Hastelloy N-Tellurium Compatibility ............................................................................................ 19 . GRAPHITE-TO-METAL JOINING ............................................................................................. ........ 19.1 Brazing of Graphite to Hastelloy N ................................................................................................ Joint Design ...................................................... .............................................. Brazing Development ........................................................................................................................ 19.2 Compatibility of Graphite-Molybdenum t3razed Joints with Molten Fluoride Salts .................. 182 182 184 185 187 190 190 192 193 196 196 200 208 208 211 212 215 217 217 217 219 221 223 226 226 227 230 230 233 236 236 236 237 237
Page 3 and 4: c c c Contract No. W-.740 5-eng- 26
Page 5 and 6: , INTRODUCTION ....................
Page 7: 7 . SYSTEMS AND COMPONENTS DEVELOPM
Page 11 and 12: i The objective of the Molten-Salt
Page 13 and 14: PART 1. MOLTEN-SALT REACTOR EXPERIM
Page 15 and 16: PART 2. MSBR DESlGN AND DEVELOPMENT
Page 17 and 18: especially when the system is stabi
Page 19 and 20: generated species in molten fluorid
Page 21 and 22: cold leg. The second loop, of Naste
Page 23 and 24: Part 1. Molten-Salt Reactor Experim
Page 25 and 26: was at full power continuously exce
Page 27 and 28: Analysis and details of operations
Page 29 and 30: 1.2 REACTlVlTY BALANCE J. R. Engel
Page 31 and 32: alance results during this time sho
Page 33 and 34: II_- - 23 Table 1.2. MSRE Cumulotiv
Page 35 and 36: 4 2 5 10 20 transient that followed
Page 37 and 38: 27 Fig. 1.13. Motor of Reactor Cell
Page 39 and 40: personnel access to the area where
Page 41 and 42: accumulation rate at present indica
Page 43 and 44: The retrieval of the sample latch w
Page 45 and 46: The moisture condensed from the cel
Page 47 and 48: MSRE, details of some of the equipm
Page 49 and 50: 39 Fig. 2.2. General View of Latch
Page 51 and 52: c 41 Table 2.1. Radiation Levels Fo
Page 53 and 54: significantly, indicating clearly t
Page 55 and 56: 2.5 PUMPS P. G. Smith A. G. Grindel
Page 57 and 58: 3.1 MSRE OPERATING EXPE RI ENCE C.
Page 59 and 60:
The rate-of-fill interlocks, includ
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16 15 44 (3 42 I1 9 51 LLETHARGY 8
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shown as solid points in Fig. 4.1 (
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These are the results of two-dimens
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. r. ~ ~ ~ Fig. 4.8. Axiol Distribu
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. 59 Fig. 4.10. Axial Distribution
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- 12 0.0 $ 04 Lo ... z ? I- ;s -04
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Part 2. MSBR Design and Development
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ather than just the core and to pro
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A . 9.
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0 2 4 6810 LLLLLLU 1 INCHES COOLING
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however, electric heaters are provi
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I 43ft 3in REACTOR ’ t 40in. ! 3i
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of machining or close tolerances. T
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GASCONN I GAS SKIRT 4ft 8in. OD 19f
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271 TIRES 2%. A PITCH L- STEAM (la
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6.1 MSBR PHYSICS ANALYSIS 0. L. Smi
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4 V S; 0.06 v F 2.25 2.24 2.23 2.22
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0 8 6 4 7- 4=H20 SPECTRUM 2=D20 SPE
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chief indicators of performance. Th
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Work related to the Molten-Salt Bre
Page 102 and 103:
I- 92 -Clt NO ClRCUl ATING BUBBLES
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L- a w r 94 ORNL-OWG 67-(1815 io‘
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about 500 mm Hg at the test operati
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1 I 1 I 1 98 MOTOR COUPLING dWER BE
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head and flow characteristics of th
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The chemical research and developme
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0 'i! m 0 w m d m w 0 W m 9 4 w lx
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Sample Nc. F312-10 FPi2-1: FP12-12
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~. 108 Table 8.2. Chemical Analyses
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tenfold or more as a consequence of
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mechanism is available which satisf
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An additional purpose of sampling w
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9. Fission Product Behavior in the
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een stripped is more nearly 50% of
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E > 0 12.0
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(014 5 2 4 o~~ 40" 5 2 5 - BLANK -~
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loi3 5 2 40’2 E : 5 m L al a 0) i
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126 Table 9.4, Fission Product Depo
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Table 9.7- Approximate Fission Prod
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(e.g., in metallic colloidal aggreg
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SAMPLES in. DlAM X t'46 in. ,,/NOR-
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c( 0 c c 0 134
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10.1 OXIDE CHEMISTRY OF ThF,-UF, ME
Page 148 and 149:
BeF, in 2LiF 13eF,, this partial pr
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(up to one week) the transparency o
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The appearance in appreciable conce
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MoF3 e h l o .... ~~ .... Mo t MoF,
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i observed peak heights for Mo 2F9
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12.1 EXTRACT] ROTACTlNlUM FROM ever
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2 a STATIC -~ -0 AGITATED A AVERAGE
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to the end of the nickel anode. A m
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centration (97% removed). The distr
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point marked with a cross is the va
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13. FB u orate 13.1 PHASE RELATIONS
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THERMOCOUPI-F FURNACE I TO VACUUM O
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Cr Metal Hastelloy N Fe Mo ~ 162 Ta
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- 0 0.44 0.40 0.36 0.32 .- + z 0.28
Page 176 and 177:
. Development and E aluation of for
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Sample No. M Wil 1 FP-9-4 FP-10-25
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LJ !+€AD POT I I I I I I I I 1 I
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This uranium species disappeared sl
Page 184 and 185:
174 BI I - CARRIER - ...... -+ SAMP
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olten- I rr Molten-salt breeder rea
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I COLD LEG RETURN LIN 178 CORE OUTL
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March 17 following the fission prod
Page 192 and 193:
Table 15.3. Comparison of Values fo
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likely cause of failure is the rapi
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186 Fig. 15.6. Inner Surfoce of Col
Page 198 and 199:
188 Fig. 15.8. Inner Surface of Cor
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on final salt samples. 'This value
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P c9 P 082 P 8'ZF P 1.11 .c OF P S0
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HFIR FUEL ELLEMENT ,EXPERIMEUT 194
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Our materials program has been conc
Page 208 and 209:
198 SPLIT STRAP SLEEVE BAND (a) S F
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others, but all three stringers in
Page 212 and 213:
- Y) a - 70 60 50 40 (0 m 30 + m 20
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204 Fig. 16.7. Photomicrographs of
Page 216:
206 Fig. 16.9. Photomicrographs of
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AXF-5QRG 4-4 4 a9g/rm3 4f 56 % ~ AX
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Carbon Corporation, Poco Graphite,
Page 223 and 224:
was found. In view of the low react
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SIC TEMPERATURE STAINLESS STEEL TUB
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18.1. IMPRQVING THE RESISTANCE are
Page 229 and 230:
These aging studies will be expande
Page 231 and 232:
221 Fig. 18.3. Hastellay N Containi
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Fig. 18.5. Hasvellcy N (Titanium Mo
Page 235 and 236:
ORWL-DWG 67-tIP39 !-in -THICK PLATE
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227 Toble 18.3. Thermal Convection
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229 ORNL-DWG 67-io980 Impurity Anal
Page 241 and 242:
231 Fig. 18.16. Hastelloy N Thermal
Page 243 and 244:
time what the effective diffusiviti
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Figure 18.20 shows an area near the
Page 247 and 248:
The third design, which is also a d
Page 249 and 250:
Part 6. Molten-Salt Processing and
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that the behavior of the rare-earth
Page 253 and 254:
22. Distillation of MSRE Fuel Carri
Page 255 and 256:
23. Steady-State Fission Product Co
Page 257 and 258:
sec (50 hr). These latter residence
Page 259 and 260:
analysis of filtered samples and th
Page 261 and 262:
25. Modifications to MSRE Fuel Proc
Page 263:
nickel line through a sintered meta
Page 267 and 268:
1. R. K. Adams 2. G. M. Adamson 3.
Page 269 and 270:
344. E. H. Taylor 345. W. Terry 346
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