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they must also provide the necessary biological shielding for the reactor. As shown in Figs. 5.6 and 5.7, the reactor cell biological shielding consists of 7-ft-thick reinforced ordinary concrete around all sides below grade and an 8-ft thickness above grade. 'The top consists of removable concrete roof plugs having 68 56ft Oin. Fig. 5.5. Reactor Cell Thermal Shield ond Component Supports. ORNL-DWG 67-406484 -1 a total thickness of 8 ft. The method of constriic- tion would be to first pour the 2-ft-thick reinforced floor pad. A 3-in.-thick carbon steel floor plate would be laid over this, and the 3-in.-steel vertical wall plates would be welded to it, the latter serv- ing as forms for pouring the side walls. A second 3-in. -thick steel plate would be erected inside the
0 2 4 6810 LLLLLLU 1 INCHES COOLING CHANNEL / 69 Fig. 5.6. Reactor Cell Construction - Component Support Penetration first with a %in. air gap between the two. A sim- ilar second plate and air gap would be provided for the floor. During reactor opetai ion, cooling air would be circulated through the gap at a ve- locity of about 50 fps to remove the heat generated by gamma absorptions in the wall. Cooling air is also used in the removable roof plugs, the air duct connections being flanged to facilitate removal. The total heat losses from the reactor cell are estimaled to be a maximum of 800,000 0RhlL-OWG 67-40644A Btu/hr. The thermal shield could tolerate loss of cooling air for up to 1 hr without an excessive temperature rise. A 3/,,-in.-lhick carbon steel membrane is in- stalled inside the inner 3-in.-thick steel wall mentioned above. This membrane is hermetically tight and would satisfy the containment leak-rate requirements. The membrane is continuous around the top plugs and also at the penetrations of the cell, as shown in Fig. 5.7. The space between it
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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
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
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: A . 9.
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 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
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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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- 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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