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ANP PROJECT PROGRESS REPORT TABLE 2.3.1. SUMMARY OF VAPOR PRESSURES FOR THE SYSTEM KF-ZrF, c, Composition Heat of Constants Vaporization Experimental Temperature (mole X) of ZrF4, &I,, Range (OC) A €3 ZrF4 KF (kcal/mole) in the relation 750-900 65.9 34.1 9.754 8,813 40.4 750-900 59.6 40.4 9.142 8,321 38.1 775-900 55.0 45.0 8.403 7,778 35.6 825-950 49.9 50.1 7.722 7,363 33.7 875-950 47.3 52.4 7.679 7,467 34.2 950- 1000 45.3 54.7 7.649 7,721 35.3 975-1 100 40.4 59.6 7.612 8,465 38.8 1 125-1 300 34.9 65.1 7.387 9,020 41.3 B log P (mm Hg) = A - - T ' where T is in OK. These constants are obtained by treating the data by the method of least squares. The heat of vaporization, AH,, of ZrF, is obtained by multiplying the constant B by 2.303 (OR) or 4.576. The values listed in Table 2.3.1 are considered to be more reliable than those previously published., Apparently there was some free ZrF, present in some of the earlier experiments, and for the compositions containing 65.9 to 49.9 mole % ZrF, a reanalysis by least squares gave the new constants. A plot of the data from which the equation for each mixture was obtained is shown in Fig. 2.3.1. A very odd phenomenon is observed when the apparent heat of vaporization, AH,, is plotted against composition (Fig. 2.3.2). A sharp minimum occurs at 50 mole % ZrF, and the heat of vaporization increases linearly with composition in both directions from the minimum. The change below 50 mole % ZrF, is in the expected direction, since ZrF, becomes more tightly complexed by fluoride ions. The change above 50 mole % was not expected; qualitatively it can be explained by assuming that ZrF, exhibits positive deviations from Raoult's law when dissolved in KZrF,. 00 (This version of Raoult's law calls for a twoparticle" depression at the ZrF, end of the composition range and for zero pressure at the KZrF, end.) In practice, the vapor pressure of supercooled liquid ZrF, is not sufficiently well 112 known for a numerically reliable Raoult law to be established for ZrF, systems at 600 to 800°C. The System RbF-ZrF, The vapor pressures of various mixtures in the system RbF-ZrF, were determined in the same manner as in the KF-ZrF, system. Reasonably pure RbF was obtained by selecting clear crystals from a slowly cooled melt. Analyses showed that the other alkali metal ions were present in the following weight percentages: Li, 0.023; Na, 0.005; K, 0.16; Cs, 0.24. The data for various mixtures are compiled in Table 2.3.2 and shown graphically in Fig. 2.3.3. The constants A and B are from the relation B log P (mm Hg) = A - - T ' where T is in OK. As in the case of the KF-ZrF, system, the heat of vaporization goes through a minimum at 50 c mole % ZrF, (Fig. 2.3.4). The linearity with mole fraction is also similar to that of the KF-ZrF, system. Thus the effect seems to be a real one in spite of its unnatural appearance. A comparison of the effects of the various alkali fluorides is given in Fig. 2.3.5, in which pressure is plotted as a function of composition at 912OC, the melting point of pure ZrF,. Moore8 has siudied two compositions for the system LiF-ZrF,, - and Sense et al.' of Battelle Memorial Institute and Moore"' have studied the NaF-ZrF, system. 8R. E. Moore, ANP Quat. Ptog. Rep. June 10, 19.55, ORNL-1896, P 81. LJ I
-0 a rn u) u) DO2 oot c ;o rn OS g 3 I s 02 008 006 000). OOtt 002 t (3e) 3HfllW&3dW31 I I L€StC SNU-Yl-1NYO a-
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Part 1 AIRCRAFT REACTOR ENGINEERING
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STATUS OF ART DESIGN Design work on
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of pressure loads. The idealized mo
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UPPER DECK 7 @ PRESSURE SHEL PERIOD
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SOD,UM r--- INCONEL TANK ROOF 0 0.5
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TABLE 1.1.1. NaK PUMP SPEEDS AND HO
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62 CALCULATED HEATING (w/crn3) N w
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where I = radius of source (taken a
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heat exchanger was used. The heatin
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head which are bounded by various t
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h bd * W - EcBRc+ ORNL-LR-DWG I4918
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PERIOD ENDlNC JUNE 10. 1956 TABLE 1
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ENRICHER ACTUATOR J. M. Eastman Spe
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hd - Thus, even with an input signa
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- . 140 120 p 100 g d 80 8 L s In y
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and lose their hardness in the pres
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p. W 2.5 0.5 0 400 OPERATING TIME (
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i 20 too 80 40 20 PERIOD ENDING JUN
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c' I - + r 500 450 400 3 50 300 2 2
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01) 0V3H 5: N 0 2 s 0 0 0 5: 0 2 s
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the first 200OF and B0F/sec for the
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PERIOD ENDING JUNE 10, 1956 TABLE 1
Page 47 and 48: L 0 _, I, -* t; - PERIOD ENDING JUN
Page 49 and 50: LJ 0.005 in. on the diameter and a
Page 51 and 52: I 3 -I W CALROD HEATER 1500 I 1400
Page 53 and 54: -17 Inconel I .._I_ I" .. _ _ ~ ._
Page 55 and 56: i E ART FACILITY F. R. McQuilkin Co
Page 57 and 58: L7i PERIOD ENDING JUNE 10, 1956 Fig
Page 59 and 60: PERIOD ENDING JUNE 10, 1956 Fig. 1.
Page 61 and 62: ART OPERATING MANUAL W. B. Cottrell
Page 63 and 64: Part 2 CHEMISTRY W. R. Grimes
Page 65 and 66: W 2.1. PHASE EQUILIBRIUM STUDIES' C
Page 67 and 68: - 0 Q 3 G 4000 900 800 700 a w a 5
Page 69 and 70: - a t a w 1000 900 000 - P 700 3 2
Page 71 and 72: - 0 e 4 000 900 800 5 700 I- a a W
Page 73 and 74: ZrF4 9t2 PERIOD ENDING JUNE 10, 795
Page 75 and 76: U c * NaF*BeF2-2NaF*BeF2 triangle c
Page 77 and 78: THE SYSTEM MgF2-CaF2 L. M. Bratcher
Page 79 and 80: 2.2. CHEMICAL REACTIONS IN MOLTEN S
Page 81 and 82: I id PERIOD ENDING JUNE 10, 1956 an
Page 83 and 84: PERIOD ENDlNG JUNE 10, 1956 V which
Page 85 and 86: u the salt-metal interface, and the
Page 87 and 88: of this reaction will be made at th
Page 89 and 90: +- + z 6 e 6 5 3 3 > k i m 3 2 2 1
Page 91 and 92: FeF,. The FeF, saturation points we
Page 93 and 94: UNIF, = yN should be unity (a pure
Page 95 and 96: Although it appears that the solubi
Page 97: , . 2.3. PHYSICAL PROPERTIES OF MOL
Page 101 and 102: IL, - PERIOD ENDING JUNE 70, 7956 O
Page 103 and 104: 8 00 700 600 - 0 0, w 500 a 3 I- U
Page 105 and 106: supporting plaque is loaded into th
Page 107 and 108: u 2.4. PRODUCTION OF FUELS c G. J.
Page 109 and 110: half of fiscal year 1957. This esti
Page 111 and 112: 2.5. COMPATIBILITY OF MATERIALS AT
Page 113 and 114: volume of 1 M tartaric acid solutio
Page 115 and 116: After the trap has been opened, bot
Page 117 and 118: \ Part 3 METALLURGY W. D. Manly
Page 119 and 120: FLUORIDE FUEL MIXTURES IN INCONEL F
Page 121 and 122: PERIOD ENDING JUNE 10, 1956 TABLE 3
Page 123 and 124: Fig.3.1.3. Region of Maximum Attack
Page 125 and 126: (d . terminated after 1217 and 1339
Page 127 and 128: - . LJ BRAZING ALLOYS IN LIQUID MET
Page 129 and 130: PERIOD ENDING JUNE 10, 1956 NaK wer
Page 131 and 132: I PERIOD ENDING JUNE 10, 1956 I Fig
Page 133 and 134: 0. PERIOD ENDING JUNE 10, 1956 Fig.
Page 135 and 136: Fig. 3.2.10. Apparatus for Studying
Page 137 and 138: STATIC TESTS OF INCONEL CASTINGS R.
Page 139 and 140: t (JnOOSll 3n918-3NOt IOH (JoOOSI)
Page 141 and 142: after the l00hr test. The extent of
Page 143 and 144: tests of the Lindsay Mix specimens,
Page 145 and 146: LJ DEVELOPMENT OF NICKEL-MOLYBDENUM
Page 147 and 148: LJ PERIOD ENDING JUNE 10, 1956 Fig.
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2. Canning of the billets with '/,-
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165 . c, e . c3 a PERIOD ENDING JUN
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u allow the billet to start through
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NEUTRON SHIELD MATERIAL FOR HIGH-TE
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PERIOD ENDfNG JUNE 10, 7956 Fig. 3.
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wrought plate used as base material
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J point. A mixture of 50-50 vol % L
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WELDING PROCEDURE: VERTICAL FIXED,
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4 2 t 4 2 in. t 2 WCLASSFKO ORNL-LR
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FABRICATION OF JOINTS BETWEEN PUMP
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* h WELDING PROCEDURE PERlOD ENDING
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1 1 6 in. PUMP BARREL t SECTION AA
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'4 x 6 x 20-in. INCONEL PLATES (/*-
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UNCLASSIFIED PHOTO 17248 Fig. 3.4.1
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through the radiator by passing col
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L, . 1 Q t V ERIOD ENDING JUNE 10,
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to permit the examination of indivi
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LJ . t L t * I LJ Fig. 3.4.33. Tube
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Fig. 3.4.37. Inner Surface of Tube
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EFFECTOF ENVIRONMENTONCREEP- RUPTUR
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PERIOD ENDING JUNE 10, 1956 UNCLASS
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Fig. 35.7. Surface Effect on the St
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44,000 42,000 40,000 - ._ (D 8000 v
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\:r 1 U UNCL 1158 W ioo,ooo 80,000
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fuel mixture (No. 30) NaF-ZrF -UF,
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i u * ‘*$ , .\. The Lindsay Chemi
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6, * c L . c e 4 gi depths greater
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i 4 Part 4 HEAT TRANSFER AND PHYSIC
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4.1. HEAT TRANSFER AND PHYSICAL PRO
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This relationship gives the ratio o
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The parameters of the’experiment
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t Fig. 4.1.7. Fuel Annulus of the V
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uncooled wall temperature that woul
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SHIELD MOCKUP REACTOR STUDY L. C. P
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Liquid (688 to 8986C) I . HT - H3Q
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THERMAL CONDUCTIVITY W. D. Powers T
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cd Fig.4.2.4. Slingers from MTR In-
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a plug when they came in contact wi
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couples were used on this loop to e
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0 20 40 60 80 lo0 I20 440 (60 180 2
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"fast" neutron in a graphite reacto
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eached thermal equilibrium in an in
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0.5 0.4 - a3 l- W z 0.2 0.1 UNCLASS
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TABLE 4.2.3. RESULTS OF EXAMINATION
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U could be evacuated was used for t
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! j * . x - iu I PERlOD ENDlNG JUNE
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CRITICAL EXPERIMENTS FOR THE COMPAC
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. I) a W PERIOD ENDING JUNE 10, 195
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U I I R i c . --. in. long, 18’4,
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I, . R t 3 4 . C 7 6 5 W 5 a c3 E4
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1 a
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ANP PROJECT PROGRESS REPORT ot(E) =
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ANP PROJECT PROGRESS REPORT TABLE 5
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ANP PROJECT PROGRESS REPORT TABLE 5
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6 ANP PROJECT PROGRESS REPORT 2 lo7
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ANP PROJECT PROGRESS REPORT GAMMA-R
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ANP PROJECT PROGRESS REPORT 5.3.3,
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ANP PROJECT PROGRESS REPORT A I P I
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ANP PROJECT PROGRESS REPORT SECTION
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ANP PROJECT PROGRESS REPORT .. .._
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