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ANP PROlECT PROGRESS REPORT 0 2 4 6 8 TOTAL NiF2 ADDED (ut % Nil UNCLASSIFIEO ORNL-LR-DWG-44634 Fig. 23.2. Comparison of Values of Solubili of NiF, in NaF-ZrF, (53-47 mole %) at 600°C Obtained By Three Investigators. compound is probably, though not necessarily, idenfical with the substance Ni F2.ZrF4 previously synthesized by Sturm. l3 Thermodynamic calculations performed prior to the experimental work indicated that if NiF, exhibited activity coefficients similar in magnitude to those previously determined for FeF,, eqvilibration at 6WoC with H,HF mixtures containing about 3% HF would allow sufficient NiF to remain in solution for satisfactory analysis. dn~y traces of NiF, (
of this reaction will be made at the conclusion of the experimental work. Experimental work is now in progress at 575OC. Efforts will be made to extend the NiF, concentration ranges and to obtain the temperature de- pendence of the equilibrium. Particular attention will be given to the determination of the activity of NiF, in the saturating phase. SOLU 6 ILI TY AN D STA B ILI TY 0 F STR UCTU RA L METAL FLUORIDES IN MOLTEN NaF-ZrF, J. D. Redman The results of studies of the stability and solubility of GF, in NaF-ZrF, (53-47 mole %) at 60OoC were presented previously. From these experiments it was concluded that the solubility of CrF, increased as the zirconium-to-chromium ratio decreased, and, accordingly, the solubility of GF, in this solvent was a function of the amount of CrF added. It was postulated that the change in soluiility was due to the separation of CrF,*ZcF, as the solid phase, with a resultant increase in the NaF concentration in the melt. Some of these experiments have been rerun in order to obtain more precise values at the larger zirconium- to-chromium ratios, and the values thus obtained, along with some of the earlier ones, are given in Table 2.2.7. 14J. D. Redman, ANP Quar. Prog. Rep. Dec. 10, 195X ORNL-2012D p 88. PERfOD ENDING JUNE 10, 1926 Similar studies have been carried out on the solubility of FeF, and NiF, in this solvent, and the data are presented in Tables 2.2.8 and 2.2.9, respectively. The data for these three structural metal fluorides also are plotted on Fig. 2.2.3. An examination of the data presented for 600OC shows that the solubility of CrF, increases quite rapidly as the zirconium-to-chromium ratio de- creases over the entire range studied. A less pronounced effect is noted for FeF,, and in the case of NiF, a slight increase is observed for the higher zirconium-to-nickel ratios. At the lower zirconium-to-nickel ratios the solubility is con- stant. These differences in behavior are shown quite clearly in Fig. 2.2.3. It appears that the solid phases present for the CrF, and FeF, sys- tems contain ZrF,, probably as MF2*ZrF4, whereas the solid phase in the NiF, system appears to tie up only very small amounts of ZrF,. It may be noted that at 800OC the solubility of NiF, is inde- pendent of the zirconium-to-nickel ratio, which suggests that the solid phase present is NiF,. There is some question regarding the reliability of the data given in the zirconium-to-sodium ratio columns in the tables, but for GF, and for FeF, at 600OC it is believed that the decrease in the ratio as the excess of metal fluoride added was increased is real. The ratio of zirconium to sodium is 0.88 in the starting material, and the consider- ably lower values found for the large additions of TABLE 2.2.7. SOLUBILITY AND STABILITY OF CrFZ IN MOLTEN NaF-ZrF4 (53-47 MOLE %) AT 60O0C Conditions of Equi li kation Found in Filtrate Cr ++ Zr-tcuCr Zr Na Zr-to-Na F G++ Total G (wt %) Ratio' (wt %) (wt %) Ratio* (wt (wt X) (wt %I 1.4 17 41.5 13.3 0.79 45.3 0.66 0.73 1.4 17 41.3 13.4 0.78 44.8 0.65 0.83 4.0 5.8 39.8 12.7 0.79 45.1 2.1 1.9 4.0 5.8 ' 39.5 129 0.78 45.2 20 1.9 6.4 3.4 38.4 13.6 0.71 44.8 3.5 3.5 6.4 3.4 38.9 141 0.70 44.3 3.4 3.6 9.6 21 37.9 13.8 0.69 44.0 5.0 5.2 9.6 2.1 36.3 13.4 0.68 44.2 5.7 59 'Ratio calculated from mole fractions. 101
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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
Page 35 and 36: p. W 2.5 0.5 0 400 OPERATING TIME (
Page 37 and 38: i 20 too 80 40 20 PERIOD ENDING JUN
Page 39 and 40: c' I - + r 500 450 400 3 50 300 2 2
Page 41 and 42: 01) 0V3H 5: N 0 2 s 0 0 0 5: 0 2 s
Page 43 and 44: the first 200OF and B0F/sec for the
Page 45 and 46: 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: u the salt-metal interface, and the
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 and 98: , . 2.3. PHYSICAL PROPERTIES OF MOL
Page 99 and 100: -0 a rn u) u) DO2 oot c ;o rn OS g
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
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STATIC TESTS OF INCONEL CASTINGS R.
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t (JnOOSll 3n918-3NOt IOH (JoOOSI)
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after the l00hr test. The extent of
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tests of the Lindsay Mix specimens,
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LJ DEVELOPMENT OF NICKEL-MOLYBDENUM
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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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