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trouble proved to be a failure in a glass seal that allowed water to enter the magnesia insulation in the cable, which is an integral part of the chamber. Safety System A period safety amplifier failed when lightning struck the power line to the reactor site, and a replacement amplifier failed as it was being installed. The field-effect transistor in this type of amplifier is susceptible to damage by transient voltages, and it was found that under some condi- tions, damaging transients could be produced when the amplifier is removed from or inserted into the system. A protective circuit was designed, tested, and installed 011 the spare unit; in the interim, a different and more stable field-effect transistor was installed. The module replacement procedure has been modified to reduce the possibility of damage incurred on installation of the module. Experience at other sites with the type of flux safety amplifiers used in the MSKE had shown that the input transistor could be damaged, causing erroneous readings, if the input signal became too large too rapidly. Therefore, a protective network of a resistor and two diodes was added to the input circuit nf each of these amplifiers. Two relays in the safety relay matrices failed, both with open coil circuits. A chattering contact on the fuel pump motor current relay caused safety channel 2 to trip several times before the problem was overcome by paralleling two contacts on the same relay. A defective switch on the core outlet temperature also caused several channel trips and one reactor scram before the trouble was identified and the switch was replaced Four rod scrams, all spurious, occurred during operation in the report period. Two were caused by general power failures during electrical storms. Ancther occurred during a routine test of the safety system when an operator accidentally failed to reset a tripped channel before tripping a second channel. :? 1 he other scram, also during a routine test, came when a spurious signal from the switch on the core outlet temperature tripped a channel while another channel was tripped by the test. TWBL SYSTEM DES3GN P. G. Herndon As experience showed the need or desirability of more information for the operators, improved per- 48 formance, or increased protection, the instrumentation and controls systems were modified or added to. During the report period there were 25 design change requests directly involving instruments or controls. Six of these required only changes in process switch operating set points. Fourteeri requests resulted in changes in instruments or controls, one was canceled, and the remaining four were not completed. The more important changes are described below. The single T32-v dc power supply formerly sewing the nuclear safety and controls instrumentation was replaced with three independent power supplies, one for each safety channel. Each obtains +32-v dc from 110-v ac, but the ac power sources arc different. One is the normal building ac system. Another is 110-v ac from a 50-kw static inverter powered by the 250-v dc system. The third comes from a 1-kw inverter operating on the 48-v dc system. Thus continuity of control circuit operation is ensured in the event of a single power supply or power source failure. It also increased the reliability of the protection afforded by the safety system by ruling out the possibility that malfunction of a single voltage-regulating circuit could compromise more than one channel. (Before the change, on one occasion, a failure in part of the regulating circuit caused its voltage output to increase from 32 to SO v, and only a second regulator in series prevented this increase from being imposed on all the safety circuits.) To prevent the reactor from dropping out of the “Run” control mode when a single nuclear safety channel is de-energized, the “nuclear sag bypass” interlocks were changed from three series-connected contacts to a two-of-three matrix. Circuits were installed to annunciate loss of power to the control rod drive circuits. This reminds the operator that he cannot imrnediately return to power simply by manually withdrawing the rods after the controls have dropped out of the “Run” inode. A wiring error in a safety circuit was discovered and corrected. Interlocks had recently been added in the “load scram” channels to drop the load wheri the control rods scram. A wiring design error resulted in these interlocks being bypassed by a safety jumper. Although the circuits were wired this way for a the before being discovered, the scram interlocks were always operative during power operation, since the reactor cannot go into the “Operate” mode when any safety jumper is inserted.
The rate-of-fill interlocks, including the pneumatic instrument components in the drain-tank weighing system, were removed from the control circuits for the fuel drain tank helium supply valve. Experience had shown that these interlocks, intended to limit the rate at which fuel could be transferred to the core, were not required, since physical restrictions in the helium supply positively prevent filling as fast as the design set point on the interlock. Four new photoengraved graphic panels incorporating recent circuit changes were installed on the control and safety circuit jumper board. The main control board graphics were also revised to show changes in the fuel off-gas system. Test circuits were originally provided to check the operability of electronic safety instruments on fuel loop pressure and overflow tank level. These were revised to make it possible to observe the value of the test signal current at which the relays operate. The measuring range of the matrix-type flow element on the upper seal gas flow from the coolant pump was increased from 5 to 12 literdhr. This was to keep the instrument 011 scale at pump bowl pressures higher than originally anticipated. A new capillary flow element was designed to replace the element that measures the reactor cell evacuation rate, raising the range from 1 to 4 liters/min. To avoid reducing the reactor system helium supply pressure below the minimum limit when large quantities of helium are required for fuel processing, the fuel processing system helium supply line was removed from the 40-psig supply header and reconnected upstream to the 250-psig main supply header. Pressureregulating instruments were installed. To provide more information to the operator, 20 additional pairs of thrrmocoiiple lead wires were installed between the vent house and the data logger. Connections at the patch panel were made available by removing unused lead wires from some radiator thermocouples. A new conduit €or these lead wires was also installed between the vent house and the existing cable trough in the coolant drain cel.1.
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c c c Contract No. W-.740 5-eng- 26
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, INTRODUCTION ....................
Page 7 and 8: 7 . SYSTEMS AND COMPONENTS DEVELOPM
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: 3.1 MSRE OPERATING EXPE RI ENCE C.
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 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
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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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