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1 I 1 I 1 98 MOTOR COUPLING dWER BEARING AND SFAl ASSEMBLY BILLOWS CONCRETE SkIELD:NG PUMP TANK MO! TEN SA1.T BEARING lNDELLER HFAT tXCHANGCR Fig. 7.5. Preliminary Layout of the MSBR Fuel Salt Pump.
Nuclear heating of the pump tank and the support structure within the pump tank is removed by circulating a portion of the fuel salt from the main salt stream over the heated surfaces. To remove the nuclear heat from the shaft, a small amount of salt is bled up the center of the shaft and fed into an annulus between the shaft and a cooling tube that extends the length of the pump tank. A labyrinth seal at the lower end of the tube forces most of the salt to flow to the upper end of the tube, where it spills over into the pump tank. An added benefit is the increased damping and stiffness provided to the shaft by the salt in the annulus. Analyses are being made of the nuclear heating in that portion of the pump casings and shaft for which no cooling is provided. if a problem is found, we can provide cooling or shielding and thermal insulation where needed to reduce the heat generation in the pump structure to an acceptable level. The seal arrangement at the upper end of the shaft is similar to that used in the MSRE salt pumps. It consists of a face-type seal (Craphitar against tool steel) with the lubricating oil on one side and the helium in the shaft annulus on the other. Helium is brought into the annulus to serve as a split purge between the salt and gaseous fission products at the lower end of the shaft and my lubricating oil that leaks through the face seal into a leak-off line. Part of the helium passes down the shaft through a close-fitting labyrinth, where the increased gas velocity reduces the upward diffusion of molten-salt vapor and gaseous fission products. Concurrently, that portion of the helium passing upward through the labyrinth seal prevents the downward movement of lubricating oil vapors and also serves to scavenge oil leakage and vapors overboard from the pump. Coolant Salt Pumps Two preliminary layouts of the XSBR coolant salt pump have been prepared. One layout utilizes a pump with a short overhung shaft mounted on two oil-lubricated irolling element bearings, and the other is a long shaft with an oil-lubricated bearing at the top end of the shaft and a molten-salt bearing located just above the impeller. One criterion for the pump requires variable-speed operation over the range 300 to 1200 rpm. The dif- 99 ficulty with the short-shaft pump is that to have the pump operate below the first critical speed, the shaft diameter would have to be greater than 8 in., which would present a formidable seal dc- sign and development problem. If it were designed to operate above the first critical and below the second critical speed, the shaft diameter would be approximately .3 in., which is inadequate to trans- mit the torque. For the long-shaft pump configuration, however, a shaft with a diameter selected on the basis of torque requirements would have a first critical speed well above the maximum operating speed. The long-shaft pump would also use the same upper bearing and seal configuration planned for the fuel and blanket salt pumps. Hence the long-shaft concept appears to be preferable for the coolant pumps. The coolant salt pump will have the impeller and volute mounted in a pump tank of sufficient volume to accommodate the thermal expansion of thc coolant salt for the most adverse thermal condition that might arise during reactor operation. A double volute pump casing has been selected to reduce ra- dial loads on the impeller and the resultant loads on the molten-salt bearing, particularly when operating at off-design conditions, and to reduce the diameter of the bridge tube, which provides a flexible connection from the volute to the pump tank nozzle. We believe that the coolant pump drive motor, although having a greater horsepower, can be designed to fit the same containment vessel as that for the fuel pump drive motor. Water Pump Test Facility Preliminary layouts have been prepared of a facility for testing the fuel pump with water. The configuration does not incorporate the long shaft of the high-temperature pump but only mocks up those portions which affect the fluid flow. The layout also includes a moclrup of the inlet to the heat exchanger tube sheet with sufficient instrumentation to monitor the flow distribution in the heat exchanger tubes. The distribution of the gas injected to remove the xenon will be monitored also. The configuration has been designed to permit water testing of the blanket pump in the same facility. The purpose of the water test facility in the pump development program is (1) to determine
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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
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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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 88 and 89: GASCONN I GAS SKIRT 4ft 8in. OD 19f
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 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
Page 138 and 139: Table 9.7- Approximate Fission Prod
Page 140 and 141: (e.g., in metallic colloidal aggreg
Page 142 and 143: SAMPLES in. DlAM X t'46 in. ,,/NOR-
Page 144 and 145: c( 0 c c 0 134
Page 146 and 147: 10.1 OXIDE CHEMISTRY OF ThF,-UF, ME
Page 148 and 149: BeF, in 2LiF 13eF,, this partial pr
Page 150 and 151: (up to one week) the transparency o
Page 152 and 153: The appearance in appreciable conce
Page 154 and 155: MoF3 e h l o .... ~~ .... Mo t MoF,
Page 156 and 157: 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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