ORNL-4191 - the Molten Salt Energy Technologies Web Site

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f 243uUF,-7biF Fuel for the J. M. Chandler Plans are nosv being made for refueling and operating the MSXE with 233U fuel early in 1968; approximately 40 kg of 233U as 233UF4-7LiF (27 and 73 mole %) eutectic salt will be required. This material must be prepared in a shielded fa- cility because of the high 232U content (240 ppm) of the 233U. The following sections describe the process, equipment, and status of the fuel preparation process. PROCESS 'The process for preparing eutectic- UF4-T,iF (27 and 73 mole %) salt for the original MSRE charge started with UF4 and LiF.' Since 233U is available only as the oxide, the process was modified. The UO, is charged to a nickel-lined vessel, and LiF is added on top of it. 'The charge is heated, under helium, to 9QOOC to melt the LiF, which wets the oxide and thermally decomposes the UO, to an average composition of U02.6. 'The charge is treated with H, to reduce the U02,6 to U02 and then hydrofluorinated with H,-HF (approximately 1O:l mole ratio) to convert the UO, to UF4. The progress of the reaction of 1J02 to form UF4 is followed by the changes in the liquidus temperature of the binary mixture as the melting point of the charge decreases from the initial melting point of 845OC for the LiF to 49OOC for the UF4-LiF (27 and 73 mole %) eutectic product. Hydrogen fluoride utilization and water production are also indicative of the progress of the reaction. After MSR Program Semiann. Progr. Hept. Feb. 28, 1965, OHNL-3812, pp. 149-50. 252 E. L. Nicholson a final H, sparge to reduce impurities, such as iron and nickel fluorides, to metals and to sweep out dissolved HF, the salt is sampled, filtered, and stored in a product container. This process has been satisfactorily tested on a small scale, and the results indicate that the processing time will be about 15 days/batch. 'Tentative plans are to make three 12-kg 233U batches of salt, which will be used for the major additions to the barren salt in the MSRE, and one 7-kg 233U batch, which will be loaded into 60 enriching capsules. EQUIPMENT AND OPERATIONS The scheiiiatic equipment flowsheet for salt preparation is shown in Fig. 26.1. The cans of U03, each containing about 500 g of uranium, will be transported in a shielded cask from the 233U storage Bcility in Building 3019 to the TURF building (7930) and introduced into cell G. All operations in cell G will be done remotely. k?y the use of manipulators, the cans will be loaded into the alpha-sealed can opener and the dunipei box, which discharges the oxide into the heated nickellined 8-in.-diarn by 3-ft-high reaction vessel and routes the empty cans to storage for subsequent removal from the cell. The 'LiF is charged to the reaction vessel via the dumper. Process gases are supplied from outside the cell, and instrumentation is provided to control gas flows and processing temperatures. Waste gases are filtered to remove entrained 233U and scrubbed with KOH to remove unreacted WF before disposal to the radioactive off-gas system. After sampling, the product is transferred via a heated
nickel line through a sintered metal filter into heated cl-in.-diam by 3-ft-high nickel product storage vessels. The caps de-filling operation is not illustrated but will consist in transferring salt horn a product vessel to an array of 60 enriching capsules in a furnace. Product vessels and enriching capsules will be stored in cell G until needed at the MSRE. KOH I STATUS Engineering design is estimated to be 95% completed, and fabrication of the equipment is 85% 253 GAS AN A LYS IS Fig. 26,l. MSRE 233U Fuel Salt Preparation System. completed. The project has been delayed because the TURF building is not completed; consequently, the cost-plus-fixed-fee (CPFF) contractor and the laboratory forces have beten delayed in starting the installation of equipment. Assuming that the building will bc available on September 15, 1967, and that the CPFF contractor and ORNI, Eorces each require dbout one month for their portions of the job, the full-scale cold run should start December 1, 1967; hot tuns should start January 20, 1968, and be completed in mid-April 1968.
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c c c Contract No. W-.740 5-eng- 26
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, INTRODUCTION ....................
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7 . SYSTEMS AND COMPONENTS DEVELOPM
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. 15.7 Oxygen Analysis ............
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i The objective of the Molten-Salt
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PART 1. MOLTEN-SALT REACTOR EXPERIM
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PART 2. MSBR DESlGN AND DEVELOPMENT
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especially when the system is stabi
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generated species in molten fluorid
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cold leg. The second loop, of Naste
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Part 1. Molten-Salt Reactor Experim
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was at full power continuously exce
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Analysis and details of operations
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1.2 REACTlVlTY BALANCE J. R. Engel
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alance results during this time sho
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II_- - 23 Table 1.2. MSRE Cumulotiv
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4 2 5 10 20 transient that followed
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27 Fig. 1.13. Motor of Reactor Cell
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personnel access to the area where
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accumulation rate at present indica
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The retrieval of the sample latch w
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The moisture condensed from the cel
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MSRE, details of some of the equipm
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39 Fig. 2.2. General View of Latch
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c 41 Table 2.1. Radiation Levels Fo
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significantly, indicating clearly t
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2.5 PUMPS P. G. Smith A. G. Grindel
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3.1 MSRE OPERATING EXPE RI ENCE C.
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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
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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
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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
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. 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
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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
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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
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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
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198 SPLIT STRAP SLEEVE BAND (a) S F
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others, but all three stringers in
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Page 214 and 215: 204 Fig. 16.7. Photomicrographs of
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Page 223 and 224: was found. In view of the low react
Page 225 and 226: SIC TEMPERATURE STAINLESS STEEL TUB
Page 227 and 228: 18.1. IMPRQVING THE RESISTANCE are
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Page 233 and 234: Fig. 18.5. Hasvellcy N (Titanium Mo
Page 235 and 236: ORWL-DWG 67-tIP39 !-in -THICK PLATE
Page 237 and 238: 227 Toble 18.3. Thermal Convection
Page 239 and 240: 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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Page 247 and 248: The third design, which is also a d
Page 249 and 250: Part 6. Molten-Salt Processing and
Page 251 and 252: 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
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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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