ORNL-4191 - the Molten Salt Energy Technologies Web Site

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iv 2.4 Development of a Scanning Device for Measuring the Radiation Level of Remote Sources .............................................................................................................................. Experiment with a 5-curie 7Cs Gamma Source ................ ................................................. Gamma Scan of the MSRE: Heat Exchanger ................................................................................... Gamma Energy Spectrum Scan of the MSRE Heat Exchanger ..................................................... 2.5 Punps ................. ....................................................................................................... Mark-2 Fuel Pum ....................................................................................................... Spare Rotary Elements for MSRE Fuel and Coolant Salt Pumps ................................................ Stress Tests of Pump Tank Discharge Nozzle Attachment ................................. MSRE Oil Pumps .............. ........................................................................................................... Oil Pump Endurance Test ................................................................................................................ 3 . INSTRUMENTS AND CONTROLS .............................................................................................................. 47 3.1 MSRE Operating Experience ........................................................................................................... 47 Control System Components ............................................................................................................ 47 Nuclear Instruments ......................................................................................................................... 47 Safety System ................................................................................................................................... 48 3.2 Conti01 System Design .................................................................................................................... 48 4 . MSRE REACTOR ANALYSIS ...................................................... ....... 4.1 Introduction ........................................................................................................................................ 4.2 Neutron Energy Spectra in MSKE and MSBR ................................................................................ 4.3 Other Neutronic Characteristics of MSRE with 233U Fuel .............. Critical Loading, Rod Worth, and Reactivity Coefficients ........................................................ Fission Rate and Thermal Flux Spatial Distributions ............................................................... Reactor-Average Fluxes and Reaction Cross Sections .............................................................. Effect of Circulation on Delayed-Neutron Precursors .............................................................. Samarium Poisoning Effects ................................................................................ 4.4 MSRE Dynamics with * 31J Fuel ................................................................................................... PART 2 . MSBR DESIGN AND DEVELOPMENT .. 5 . DLSIGN ............................................................................................. ..................................... 5.1 General ............................................................................................................................................. 5.2 Cell Arrangement ........................................................................................... .............................. 5.3 Reactor .............................................................................................................................................. 5.4 Fuel Heat Exchanger .......................... ....................................................................... 5.5 Blanket Heat Exchanger .................................................................................................................. 5.6 Fuel Drain Tanks ................................ ..................................................................................... 5.7 Blanket and Coolant Salt Drain Tanks .......................................................................................... 5.8 Steam Generator-Superheater and Reheater ................................................................................ 6 . REACTOR PHYSICS .................................................................................................................................... 82 6.1 MSBR Physics Analysis ...................................................... ....... ......... .. . . Optimization of Reactor Parameters .............................................................................................. 82 82 Useful Life of Moderator Graphite .................................................................................................. 84 Flux Flattening .............................................................................................................................. 87 Temperature Coefficients of Reactivity ........................................................................................ 88 40 41 43 43 45 45 45 46 46 46 50 50 50 54 54 55 55 58 60 61 63 63 65 71 76 76 79 79 81
7 . SYSTEMS AND COMPONENTS DEVELOPMENT .................................................................................... V 7.1 Noble-Gas Behavior in the MSRR ...................................... ............................... ... '7.2 MSBR Fuel Cell Operation with Molten Salt ................................................................................ 7.3 Sodium Fluoroborate Circulating Loop Test .... ............................................. 7.4 MSBR Pumps .......................... ................................................................................................... Survey of Pump Experience lating Liquid Metals and Molten Salts ................................ Introduction of MSBR Pump Program .............................................................................................. Fuel and Blanket Salt Pumps ....................................................... .......................................... Coolant Salt . Pumps ........................................................................................................ Water Pump Test Facility .... .................................................................................................... Molten-Salt Rearing Tests ......................................... ............................................................. Rotor-Dynamics Feasibility Invest.igation .................................................................................... Other Molten-Salt Punips .................................................................................................................. PART 3 . CHEMISTRY 8 . CHICMISTRY OF THE MSRE ................ ......... ................... 102 8.1 MSRE Salt Composition and Purity ................................................................................................ 102 Fuel Salt ................................ .......................... .................................. ..................... 103 Coolant Salt ...................................................................................................................................... 103 Flush Salt ........................... .............................................................................................. 103 Implications of Current Ex in Future Operations .......................................................... 108 8.2 MSRE Fuel Circuit Corrosion Chemistry ........ ................................. 8.3 Adjustment of the UF, Concentration of the Fuel Salt .......................................... 9 . FISSION PRODUCT BEHAVIOR IN THE MSRE ...................................................................................... 116 9.1 Fission Products in MSRE Cover Gas .......................................................................................... 116 9.2 Fission Products in MSRE Fuel .................................................................................................... 119 9.3 Examination of MSKE Surveillance Specimens After 24, 000 Mwhr ........ ............................... 121 Examination of Graphite .......................................................... .................................................. 121 Examination of I-Iastelloy N ...................................... .................................................. 124 Fission Product Distribution in MSRE ..................... ....................................................... 125 9.4 9.5 Deposition of Fission Products from MSRE Gas Stream on Metal Specimens ........ Deposition of Fission Products on Graphites in MSRE Pump Bowl ......................................... 10 . S'TUDIES WITH LiF-BeF2 MELTS .............................................................................. ................... 136 10.1 Oxide Chemistry of ThF,-UF, Melts .......................... ................................................. 136 10.2 Containment of Molten Fluorides in Silica .................. ................................................. 137 Chemistry ........................................................................ ................... 137 Spectrophotometric Measurements with Silica Cells ................... ................... 139 10.3 Electrical Conductivity of Molten Fluorides and Fluoroborates ............ ...................... 140 11 . BEHAVIOR OF MOLYBDENUM FLUOKIDES ................................................................. 142 11.1 Synthesis of Molybdenum Fluorides .............................................................................................. 142 11.2 11.3 Reaction of Molybdenum Fluorides with Molten LiF-BeF, Mixtures ................ Mass Spectrometry of Molybdenum Fluorides ........................................................ 90 90 95 95 96 96 96 97 99 99 100 100 101 1.31
Page 3 and 4: c c c Contract No. W-.740 5-eng- 26
Page 5: , INTRODUCTION ....................
Page 9 and 10: . 15.7 Oxygen Analysis ............
Page 11 and 12: i The objective of the Molten-Salt
Page 13 and 14: PART 1. MOLTEN-SALT REACTOR EXPERIM
Page 15 and 16: PART 2. MSBR DESlGN AND DEVELOPMENT
Page 17 and 18: especially when the system is stabi
Page 19 and 20: 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.
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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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- 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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