ORNL-4191 - the Molten Salt Energy Technologies Web Site

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62 Table 4.5. Comparison of MSRE Nuclear Data for 233U- and 235U-Bearing Fuel Salts Static delayed-neutron fractions, b, and precursor decay constants, (sec- ’) .......... .......... ......... ......... ..... .................. .......... Group 1 2 3 4 5 6 Total static ,3 Prompt-neutron generation time, sec Temperature coefficients of reactivity, (OF)-’ Fuel salt Graphite 23 3 u 235u ...... ........... ‘i ”; Al Pi 0.0126 0.228 x 0.0337 0.788 x lop3 0.139 0.664 lop3 0 325 0.736 x lop3 1.13 0.136 X 2.50 0.088 x 0.00264 4.0 Y 10 -6.13 x lop5 -3.23 x lop5 0.0124 0.223 X lor3 0.0305 1.457 x 0.111 1.307 x 0.301 2.628 x 1.14 0.766 x lor3 3.01 0.280 x lop3 0,00666 2.4 x -4.84 + lo-’ -3.70 lor5 ORNL DWG 67 11805 OOf 002 005 01 02 05 I 2 5 IO POWEP LEVEL (Mw) Fig. 4.13. Comparison of MSRE Predicted Phase Margins and Natural Periods of Oscillation vs Power Level for 233U- and 235tJ-Bearing Fuel Salt Loadings.
Part 2. MSBR Design and Development R B. Briggs The primary objective of the engineering design and development activities of the MSR program is to design a molten-salt breeder experiment (MSBE) and develop the components and systems for that reactor. The MSBE is proposed to be a model of a large power breeder reactor and to operate at a power level of about 150 Mw (thermal). A reference design of ii 1000-M~ (electrical) molten-salt breeder reactor power plant is to provide the basis for most of the criteria and for much of lhe design of the MSBE. We have been spending mosi of our effort on the reference design. Several concepts were described in ORNL-4037, our progress report for the period ending August 1966, and in OKNL-3996, which was published in August 1966. We selected the modular concept - four 250- Mw (electrical) reactors per 1000-Mw (electrical) station - that has fissile and fertile materials in separate streams as being the most promising for irnmediate development and have proceeded with moie detailed study of a plant based on that concept. Initial results of those studies were reported in ORNL-4119, our progress report for the 5.1 GENERAL E. S. Bettis R. C. Robertson The design program during the past period has primarily been directed toward refinement and modification of the previously reported concepts for the reactor and other major equipment and re- visions to the cell layouts and piping. 5. Design E. s. Uettis 63 period ending February 1967. During this report period, we continued to examine the details of the reference plant and its equipment. We also summarized the objectives and program for dcvelopment of the MSBE in OHNL-TM-1851. To date, the component and systems development activity has been concerned largely with support of the design and with planning. The development program was outlined in ORNL-TM-1855 and in ORN L-TRiI-1856. Salt circulation hops and other test facilities are being modified for tests of the sodium fluoroborate coolant salt, models of graphite fuel cells for the reactor, and molten-salt bearings and other crucial components of the fuel circulation pump, Essentially no experimental work has been done yet. We plan to complete essential parts of the reference design during the next report period and to bpgin lo design the MSRE. Experimerital work will begin also hut will be limited to a Eew of the more obvious important problems. Desiyg and development on a large scale are planned to start early in FY 1969. The major effort was redesign of the reactor to accommodate the new data on radiation effects in graphite. New approaches were tried to arrivc at a core design which could cornpcnsate for dimen- sional changes in the graphite, but it was finally decided to simply double the volume of the core to lower the power density from 40 to 20 kw/liter and thereby assure a stable core life of at least ten years. It was also decided to include pro- visions for replacing the complete reactor vessel
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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
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
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: - 12 0.0 $ 04 Lo ... z ? I- ;s -04
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 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
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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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- 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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