ORNL-4191 - the Molten Salt Energy Technologies Web Site

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Effective “one group” cross sections were calculated from results from OPTIMERC (a reactor analysis code) for the MSBR reference design. The fuel salt was assumed to be completely mixed, and capture terms were reduced by a factor equal to the ratio of the core volume to the total fucl salt volume. Heat-generation rates, both at the instant of removal from the reactor and after various decay periods, were calculated from the steady-state fission product concentrations in the fuel using CALDRON, a fission product heat-generation and decay code. Heat-generation rates obtained with 235U yields were in good agreement with rates calculated by a modified (to treat a steady-state reactor with continuous processing) version of PHOSE, a code written by E. D. Arnold and based on experimental data for decay of fission products. Agreement with a reputahle code indicates that the simplifications in the present calculations were reasonable. In the MSRR, some fission products will be removed from the fuel by the gas purge or by plating on solid surfaces, and other fission products will be removed in processing (fluorination) before the t a w r lo3 I O0 246 salt reaches the still. Removal of fission products by plating and gas stripping was taken into account by assigning appropriate residence times, Tz, for volatile or noble elements. After withdrawal from the reactor, the fuel salt was assumed to be re- tained in a hold tank for 12 hr, after which specified fractions of elements havjng volatile fluorides were removed. The remaining fission products were then allowed to decay for an additional 12 hr before entering the still. Figure 23.1 shows fuel salt heat-generation rates calculated for various times after removal from the reactor. ‘These calculations were made with MSRK design conditions: 2220 Mw (thermal), 3.7 x iO14 neutrons sec-’ cm-’, cote volume of 9400 liters, fuel salt volume of 25,400 liters, and 4.5 x lo6 sec (52 days) processing cycle. The uppermost curve represents no fission product removal in the reactor or in the fluorinator. ‘The next lower solid curve represents Kr and Xe removal from the reactor with a 30-sec residence time, and the lowest solid curve represents removal of Kr and Xe (30-sec residence) along with removal of Mo, Tc, Ru, X
sec (50 hr). These latter residence times are rough estimates, and as better information becomes available from fission product behavior in the MSKE, more reliable estimates of the residence times for these elements will be possible. This lowest solid curve in Fig. 23.1 is shown only to suggest the general range of conditions under which the fuel processing plant may operate. The dashed curves in Fig. 23.1 were obtaincd from the same reactor calculations, but some fission products were assumed to be removed in the fluorinator. The elements Xe, Kr, Rt, I, Mo, Tc, Te, and Se were considered to be completely removed, and 15% of the Ru, Rh, Nb, and Sb were removed. After fluorination, however, these elements may “grow’’ back into the system. HEAT GENERATION IN A MOLTEN-SALT STILL Buildup of heat generation in a molten-salt distillation system was calculated using the heat- generation data given in Fig. 23.1. The reactor and that part of the processing system prior to the still were assumed to be at steady state, although the transient associated with buildup of fission products in the still was considered. Fuel salt containing fission products remaining after fluorination was fed to a distillation system, and complete retentjon of fission products was assumed. The fuel salt was assumed to have been held up 24 hr in processing prior to entering the still (12 hr before fluorination and 12 ht after). The heat-generation data from Fig. 23.1 was fitted by the method of least squares to the rela- tion 247 where H(t) == heat-generation rate at time t (Htu hr- 1 ft.-’3 ), A,, k. ::: constants, 1 1 t ::: time after salt leaves fluorinator (days). The rate of heat generation in the still is then given as where Q(r) = heat generation in still after operating for a time t (Wtu/hr), F - fuel salt processing rate (ft3/day), t - length of time still has operated (days). Calculated heat-generation ratcs in the still are shown in Fig. 23.2 for a piocessing rate of 15 ft3/day for several assumed removal efficiencies (the same assumptions noted for Fig. 23.1) in processing steps prior to the still. The still system will be near steady state in two to three years, and heat generation rates as high as 3.0 Mw can be expected. Removal of fission products by gas stripping, plating on metal surfaces, and formation of volatile fluorides during fluorination will reduce this rate to about 2.2 Mw, ORNL-DWG 67-9/38A Fig. 23.2. Fission Product Decay Heat in MSBR Still and Accumulation Tank.
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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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HFIR FUEL ELLEMENT ,EXPERIMEUT 194
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
Page 216: 206 Fig. 16.9. Photomicrographs of
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Page 221 and 222: Carbon Corporation, Poco Graphite,
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
Page 229 and 230: These aging studies will be expande
Page 231 and 232: 221 Fig. 18.3. Hastellay N Containi
Page 233 and 234: Fig. 18.5. Hasvellcy N (Titanium Mo
Page 235 and 236: ORWL-DWG 67-tIP39 !-in -THICK PLATE
Page 237 and 238: 227 Toble 18.3. Thermal Convection
Page 239 and 240: 229 ORNL-DWG 67-io980 Impurity Anal
Page 241 and 242: 231 Fig. 18.16. Hastelloy N Thermal
Page 243 and 244: time what the effective diffusiviti
Page 245 and 246: Figure 18.20 shows an area near the
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 and 254: 22. Distillation of MSRE Fuel Carri
Page 255: 23. Steady-State Fission Product Co
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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