ORNL-4191 - the Molten Salt Energy Technologies Web Site

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GASCONN I GAS SKIRT 4ft 8in. OD 19ft Oin COOLANT 20in NPS 1 8113 NPS I 2ftOin 1 78 ~ , I 8in I ORNL-DWG 67-40679.1 PAOTOR FLANGE S?OOL OPERATING LEVEL MOL-TEN SALT BEARING BLANKET PROCESSING DRAIN LINE BLANKET TO REACTOR 8in NPS i FLANGE I IMPELLER 8ft 4in Fig, 5.12. Blanket Heat Exchanger and Pump. 250 Mw (electrical) unit. 1 ou mi 1 UBES 822 AT 3/8~n. OD INNER rUBES 834 AT 3/8in OD
Table 5.4. Blanket Heat Exchanger Specifications Number required Rate of heat transfer, Nw Eate of heat transfer, Btu/hr Shell side Hot fluid or cold fluid Entrance temperature, OF Exit temperature, OF Entrance pressure, a psi Exit pressure,a psi Ai’ across exchanger, psi Mass flow rate, Ib/h Tube side Not fluid or cold fluid Entrsnce temperature, “F Exit temperature, OF Entrance pressure,” psi Exit pressure,a psi i\P across exchanger, psi Mass flow rate, Ib/hr Velocity, fps Tube material Tube OD, in. Tube thickness, in. Tube length, tube sheet to tube sheet, ft Shell materiel Shell thickness, in. Shell ID, in. Tube sheet material Tiibe sheet thickness, in. Number of tubes Inner annulus Outer annulus 1 Pitch of tubes, in. Total heat transfer area, ft2 Basis for area calculation Type of baffle Number of baffles Rafkle spacing, in. Disk OD, in. Doughnut ID, in. Overall heat transfer coef- ficient, U, &tu hr-’ ft-2 aIncludes pressure due to gravity head. bPressnre loss due to friction only. 4 27.8 9.47 107 Cold (coolant salt) 1110 1125 138 129 15 1.63 x 10’ Hot (blanket salt) 1250 1150 111 20 91 4.3 x 106 10.5 Hastelloy N 0.375 0.035 8.3 Hastelloy N 0.50 55 Hastelloy N 1 83 4 822 0.8125, triarigiilar 1318 Tube OD Disk and doughnut 4 19.8 33.6 31.8 1030 79 5.6 FUEL DRAIN TANKS H. L. Watts T. W. Pickel Two 60-iti.-diam by 20-ft -high dump tanks are required for draining the fuel salt from each of the reactor systems. These ate shown in Fig. 5.13. One drain tank is connected to the 5-in.-diam overflow connection on the sump tank of the fuel circulating pump and receives all tht3 salt from the reactor when it is drained. The drain time is estimated to be short, probably less than 10 sec, and this method could be used for emergency shutdown if necessary. The other drain tank is connected to the fuel heat exchanger and fills through a siphon action due to the differences in elcvat i on. The maximum heat to be removed in each fuel drain tank is 12 Mw (thermal). The two tanks are cooled by a total of 422,000 lt)/hr of steam taken from the high-pressure turbine-generator exhaust at about 550 psia. ‘The steam is heated from G O O F to about 1000OF in vertical thimblcs spaced on 3- in. centers in each dump tank. There are 271 of these thimbles per tank, extending to within 1 in. of the hot tom. The reentrant -type steam thimbles are inserted in 2-in.-OD INOR-8 thimbles which contact the fuel salt, the 0.025-in. radial clearance between the two thimbles being filled with stag- nant inert fuel salt to serve as a heat transfer medium. The double thimble arrangement provides the necessary double barrier between the steam and the enriched fuel salt. Steam leaves the thimbles at about 72 fps and enters the steam chest at the top of the dump tank. 5.7 BLANKET AND COOLANT SALT DRAIN TANKS H. L. Watts W. C. George The drain tanks for the blanket salt and for the secondary coolant salt are essentially simple storage reservoirs. Cooling systems such as those used in the fuel salt tanks are not required. ‘The details of the designs for these tanks have not been completed. The location of the tanks in the cells is shown in Fig. 5.3.
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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
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
Page 61 and 62: 16 15 44 (3 42 I1 9 51 LLETHARGY 8
Page 63 and 64: shown as solid points in Fig. 4.1 (
Page 65 and 66: These are the results of two-dimens
Page 67 and 68: . r. ~ ~ ~ Fig. 4.8. Axiol Distribu
Page 69 and 70: . 59 Fig. 4.10. Axial Distribution
Page 71 and 72: - 12 0.0 $ 04 Lo ... z ? I- ;s -04
Page 73 and 74: Part 2. MSBR Design and Development
Page 75 and 76: ather than just the core and to pro
Page 77 and 78: A . 9.
Page 79 and 80: 0 2 4 6810 LLLLLLU 1 INCHES COOLING
Page 81 and 82: however, electric heaters are provi
Page 84 and 85: I 43ft 3in REACTOR ’ t 40in. ! 3i
Page 86 and 87: of machining or close tolerances. T
Page 90 and 91: 271 TIRES 2%. A PITCH L- STEAM (la
Page 92 and 93: 6.1 MSBR PHYSICS ANALYSIS 0. L. Smi
Page 94 and 95: 4 V S; 0.06 v F 2.25 2.24 2.23 2.22
Page 96 and 97: 0 8 6 4 7- 4=H20 SPECTRUM 2=D20 SPE
Page 98 and 99: chief indicators of performance. Th
Page 100 and 101: Work related to the Molten-Salt Bre
Page 102 and 103: I- 92 -Clt NO ClRCUl ATING BUBBLES
Page 104 and 105: L- a w r 94 ORNL-OWG 67-(1815 io‘
Page 106 and 107: about 500 mm Hg at the test operati
Page 108 and 109: 1 I 1 I 1 98 MOTOR COUPLING dWER BE
Page 110 and 111: head and flow characteristics of th
Page 112 and 113: The chemical research and developme
Page 114 and 115: 0 'i! m 0 w m d m w 0 W m 9 4 w lx
Page 116 and 117: Sample Nc. F312-10 FPi2-1: FP12-12
Page 118 and 119: ~. 108 Table 8.2. Chemical Analyses
Page 120 and 121: tenfold or more as a consequence of
Page 122 and 123: mechanism is available which satisf
Page 124 and 125: An additional purpose of sampling w
Page 126 and 127: 9. Fission Product Behavior in the
Page 128 and 129: een stripped is more nearly 50% of
Page 130 and 131: E > 0 12.0
Page 132 and 133: (014 5 2 4 o~~ 40" 5 2 5 - BLANK -~
Page 134 and 135: loi3 5 2 40’2 E : 5 m L al a 0) i
Page 136 and 137: 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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- Y) a - 70 60 50 40 (0 m 30 + m 20
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204 Fig. 16.7. Photomicrographs of
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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,
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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
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These aging studies will be expande
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221 Fig. 18.3. Hastellay N Containi
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Fig. 18.5. Hasvellcy N (Titanium Mo
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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
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231 Fig. 18.16. Hastelloy N Thermal
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time what the effective diffusiviti
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Figure 18.20 shows an area near the
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The third design, which is also a d
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Part 6. Molten-Salt Processing and
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that the behavior of the rare-earth
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22. Distillation of MSRE Fuel Carri
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23. Steady-State Fission Product Co
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sec (50 hr). These latter residence
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analysis of filtered samples and th
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25. Modifications to MSRE Fuel Proc
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nickel line through a sintered meta
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1. R. K. Adams 2. G. M. Adamson 3.
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344. E. H. Taylor 345. W. Terry 346
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