ORNL-4191 - the Molten Salt Energy Technologies Web Site

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alloy No. 25, and an experimental alloy (alloy No. 82) having the composition 18 Mo-0.2 Mm--0.05 Cr-bal Ni. Activities associated with the system during the past two months and scheduled activjties through completion of radioactive operation are shown in Fig. 22,l. Still fabrication has been completed, and the thermal insulation and electric heaters have been received. Four faulty heaters out of a total of 41 were rejected, and replace- ments have been ordered. Instrumentation work is 90% complete. The first of several 48-liter salt charges for nonradioactive operation is being prepared by Reactor Chemistry Division personnel. Experiments using nonradioactive salt will begin 244 in early October and will continue through Feb- ruary 19G8. The still will then be inspected for radioactive operation and installed at the MSRE site in the spare cell adjacent to the fuel processing cell. The equipment will then be used for distilling 48 liters of radioactive MSKE fuel salt (decayed 90 days) from which uranium has heen removed by fluorination. It was determined that the roof plugs in the spare cell do not provide adequate biological shielding for 90-day-old salt; the plugs have been redesigned and will consist of 30-in.-thick barytes concrete rather than the present 24-in. ordinary conciete.
23. Steady-State Fission Product Concentrations and Heat Generation in an MSBR and Processing Plant Concentrations of fission products and the heat generation associated with their decay are re- quired for design of systems €or processing the fuel and fertile streams of an MSBR. A method for calculating the steady-state concentration of fission products in an MSBR will be described, and heat-generation rates in the fuel stream will be given. Changes in heat-generation rate re- sulting from removal of fission products in both the reactor and the fuel-stream processing system will be shown. Several simplifying assumptions were made in calculating the concentration of fission products in the fuel stream of an MSBR. The differential equation used to define the concentration of a given isotope was where J. S. Watson L. E. McNeese W. L. Carte1 Nz,A = number of atoms of an isotope with atomic number 2 and mass number A, . .. .. . .- Vc/V, = core volume/total fuel volume, T - processing cycle time €or isotopes z with atomic number 2 (sec), t : time (sec). The reactor was assumed to be at steady state with respect to all fission products. At steady state, dN /dt -: 0; so the differential equation reduces to Z,A which defines the steady-state Concentration of each isotope. This equation was solved for each isotope using an IHM 7090. The calculations used 235U yields given by Blomeke and Todd;' yields for 233U were obtained by distributing "mass yields" reported by England' among the isotopes in each mass chain so that each isotope had the same fraction of the mass yield as reported for 235U. Decay chains were simplified and approxi- mated by "straight" chains considering only beta decay. Where isomeric transitions or other complications were noted, personal judgment was used to approximate the res1 process with straight beta decay. P - power (w), Y = primary yield of isotope of atomic number and number A (atoms/ ' 1. 0. Rlomeke . and Marv ,- F. Todd. Umninm-235 ~ Fission-Product Production as a Function of Thermal Neutron I'lux, Irradiation Time, and Decay Time. 1. Atomic Coricentrafions and Gross Totals, ORNL-2127 f iss i on), + = flux (neutrons sec-' cm-'), (part I.), vol. 1. 'T. R. England, Time-Dependent Fission-Product (2 7 cross section of isotope with atomic %,A number 2 and mass number A (cm'), '~liemia? andKesonance Absorption Cross Sections matil Revisions azld Colculationa1 Extensions), WAPD- TM-333, addendum No. 1. 245
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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
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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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Page 206 and 207: Our materials program has been conc
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Page 210 and 211: others, but all three stringers in
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Page 214 and 215: 204 Fig. 16.7. Photomicrographs of
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Page 219 and 220: AXF-5QRG 4-4 4 a9g/rm3 4f 56 % ~ AX
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Page 223 and 224: was found. In view of the low react
Page 225 and 226: SIC TEMPERATURE STAINLESS STEEL TUB
Page 227 and 228: 18.1. IMPRQVING THE RESISTANCE are
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Page 235 and 236: ORWL-DWG 67-tIP39 !-in -THICK PLATE
Page 237 and 238: 227 Toble 18.3. Thermal Convection
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Page 241 and 242: 231 Fig. 18.16. Hastelloy N Thermal
Page 243 and 244: time what the effective diffusiviti
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Page 247 and 248: The third design, which is also a d
Page 249 and 250: Part 6. Molten-Salt Processing and
Page 251 and 252: that the behavior of the rare-earth
Page 253: 22. Distillation of MSRE Fuel Carri
Page 257 and 258: sec (50 hr). These latter residence
Page 259 and 260: analysis of filtered samples and th
Page 261 and 262: 25. Modifications to MSRE Fuel Proc
Page 263: nickel line through a sintered meta
Page 267 and 268: 1. R. K. Adams 2. G. M. Adamson 3.
Page 269 and 270: 344. E. H. Taylor 345. W. Terry 346
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