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ANP PROJECT PROGRESS REPORT 120 TABLE 2.3.4. SURFACE TENSION MEASUREMENTS ON NaF-ZrF4 (53-47 MOLE W) Temperature Sample Weight Weight Loss Final Composition* Density Surface Tension x/z (OC) (9 ) (%I (mole % ZrFJ (9/cm3) (dynes/cm) ~ ~ ~~~~ ~ ~ ~ ~ 601 ** 0.870 28.2 36 d 1.71706 3.043 141 603** 0.870 28.2 36.6 1.66592 3.040 141 61 1 0.4502 3.1 43.5 1.53637 3.030 141 61 0 0.4502 3.1 43.5 1.56345 3.031 134 601 0.4502 3.1 43.5 1.60542 3.043 122 601 0.4502 3.1 43.5 1.57069 3.043 132 601 Od502 3.1 43.5 1.55482 3.043 136 601 0.4502 3.1 43.5 1.56994 3.043 131 610 0.5097 3.7 41.4 1.68795 3.031 117 610 0.5097 3.7 41.4 1.65982 3.031 124 6 02 -. 0.5 097 3.7 41.4 1.64464 3.043 128 *Calculated from anolysis of material after test. **Tested in vacuum; all other samples tested under helium atmosphere. TABLE 2.3.5. CONSTANTS OF EQUATION FOR SPECIFIC CONDUCTANCE, K, OF FUSED LITHIUM, POTASSIUM, AND CESIUM FLUORIDES K = a + (b X lo’*), + (c x 10-6)t2, ohm-l-cm’l, where t is in OC Salt a b c Standard Deviation Applicable Temperature (ohm-’ Scm‘’) Range (‘C) LiF + 3.805 + 1.004 -3.516 0.008 847-1027 KF -3.493 + 1.480 -6.608 0.009 - 869-1040 CsF -4.51 1 + 1.642 -7.632 0.009 Salt a TABLE 2.3.6. CONSTANTS OF EQUATION FOR DENSITY, p, OF FUSED LITHIUM, POTASSIUM, AND CESIUM FLUORIDES LiF 2.2243 0.4902 KF 2.4685 0.651 5 p = a - (b x 9/cm3, where 1 is in OC b 725-921 Standard Deviation, Experimental Temperature (7 (s/cm3) Range PC) 0.0003 0.0003 876-1 047 881-1 037 Cs F 45489 1.2806 0.0004 712-912 * *
u 2.4. PRODUCTION OF FUELS c G. J. Nessle G. M. Watson L. G. Overholser I EXPERIMENTAL PREPARATION OF c tid VARIOUS FLUORIDES B. J. Sturm Continued use of structural metal fluorides for research necessitated the preparation of additional quantities of these materials by the several methods developed previously. As in the past, use was made of chemical, x-ray, and petrographic examinations to establish the identity and purity of the materials. Additional CrF, was prepared by hydrofluorination of anhydrous CrCI,, as well as by the thermal decomposition of (NH ) CrF6. The latter is pre- 4.3 pared by the interaction of hydrated CrF, with NH,F.HF, and it may also be reduced by hydrogen to yield CrF,. Several batches of NiF, were prepared by the hydrofluorination of either hydrated NiF, or hydrated NiCI,. One batch of AgF was prepared by hydrofluorination of AG,CO,. Methods described previously’ were used for the preparation of additional quantities of CeF, and of LaF,. An attempt to remove oxide from a KF-ZrF, mixture by hydrofluorination was unsuccessful. Runs at 60OOC failed to remove the oxide completely and, while this could be accomplished at 85OOC, the loss of ZrF, was sufficient to alter the composition to the point where the material was unsatisfactory for its intended purpose. A batch of CuF, was prepared for use as a carrier in certain spectrographic boron analyses. Material low in boron and silicon was requested for this purpose. Anhydrous CuF, was hydrofluorinated for 4 hr at 4OO0C, but this short period of treatment failed to reduce the boron content to a sufficiently low level. However, extending the period of hydrofluorination to 20 hr terial that was acceptable. A fuel mixture containing Li7 and nium was prepared for radiation damage studies. Since Li7 was available only as the carbonate, a preliminary run was made with normal Li,CO, UF, KF, NaF, and excess NH,F*HF to establish whether fusion of this mixture would yield an oxide-free product. After the prel iminary run proved successful the procedure was applied to the mixture containing Li’ and U2,’. The material was PERIOD ENDING JUNE 10, 1956 oxide free, but a sulfur content of 170 ppm was reported, most of which came from the LiiCO,. The fuel was subjected to 5 cycles, each of which entailed a 10- to 15-hr hydrogen treatment and 1 hr of hydrofluorination at 80OoC. The product then contained 45 ppm of sulfur and a trace of oxide, Hydrofluorination at 70O0C for 6 hr then produced an oxide-free product. LABORATORY-SCALE PURIFICATION OPE RATIONS F. L. Daley W. T. Ward With appropriate modifications, the standard hydrofluorination-hydrogenation process was used to prepare a number of especially pure materials requested for various purposes. Of these only an NaF-ZrF,-UF, mixture containing additives of BaF,, LaF,, and RbF had not previously been prepared by the standard procedure. operational foci I- ities to transfer and dispense small samples (200 to 500 g), especially into apparatus for accurate evaluation of physical properties of materials, were constructed and used successfully during this quarter. There is evidence that direct transfer of the purified melt into the apparatus has significantly improved the purity of the test material and, ac- cordingly, increased confidence in the test results. Copper-I ined stainless steel reactors were used successfully in the purification operations. P ILOT-SC AL E PUR I FICATION OP ER AT IONS J. P. Blakely C. R. Croft J. Truitt e pilot-scale purification facility processed 68 es totaling approximately 1300 Ib of various de compositions for use in small-scale corro- sion testing, phase equilibrium studies, and physical property studies. The bulk of the materiai was produced during February when the facility was operating on a threeshift, 24-hr-day basis. As a result, the backlog reported last quarter was eliminated and normal operations were resumed. ’B. J. Sturm, ANP Quat. Pmg. Rep. March 10, 1956. ORNL-2061, p 100. 121
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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
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L 0 _, I, -* t; - PERIOD ENDING JUN
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LJ 0.005 in. on the diameter and a
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I 3 -I W CALROD HEATER 1500 I 1400
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-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 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: supporting plaque is loaded into th
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.
Page 149 and 150: 2. Canning of the billets with '/,-
Page 151 and 152: 165 . c, e . c3 a PERIOD ENDING JUN
Page 153 and 154: u allow the billet to start through
Page 155 and 156: 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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