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ANP PROJECT PROGRESS REPORT 86 4:) 5.37 4.67 4.21 4.1 1 3.98 3.82 3.72 3.56 3.52 3.44 3.3 1 3.22 3.12 3.1 1 3.07 3.01 2.95 2.571 2.482 2.356 2.243 2.164 2.111 2.088 2.060 2.025 2.004 1 e976 1.947 1.909 1 a861 1.812 1.727 1 a638 1 e591 I/$ 30 9 37 10 15 22 30 5 11 100 8 30 63 100 5 20 6 10 8 8 8 10 15 15 33 30 8 7 28 18 85 6 10 10 10 THE SYSTEM NoF-RbF-ZrF4-UF4 w H. A. Friedman H.. Davis7 I Two areas of the quaternary system NaF-RbF- ZrF,-UF, offer mixtures which may be suitable fuels for circulating-fuel reactors. Solvents with approximately 10 mole % NaF, 52 mole % RbF, and 38 mole % ZrF, with the addition of 4 mole % UF, give a fuel with a liquidus temperature of approximately 500°C. With the addition of 7 mole % UF, a fuel with a liquidus temperature of approximately 545°C is obtained. These fuel mixtures have RbF-UF, or RbF*3UF4 as the primary phase. No serious segregation of the uranium phase has been evident in the experi- , mental work. These mixtures are not optimal choices for the fuel mixture because the uranium phase contains a high concentration of UF, and there is a large difference between the temperatures at which the uranium phase and the primary phase of the solvent separate. Solvents with approximately 35 mole 96 NaF, 25 mole % RbF, and 40 mole % ZrF, with the f addition of 4 mole % UF, give a fuel with a liquidus temperature of approximately 480%. With the addition of 7 mole % UF, a fuel with a liquidus temperature of approximately 51 O°C is obtained. At both UF, levels the uranium is contained entirely in the solid solution 7NaF.6Zr(U)F4. Mixtures of this general type should have physical ’ properties and corrosion characteristics that would make them of definite interest as fuels. THE SYSTEM NaF-LiF-BeF, R. E. Meadows Quenching studies of the system NaF-LiF-BeF, were continued, and it is now possible to present a diagram (Fig. 2.1.6) of the triangle having LiF, NaF, and NaF-BeF, at the apexes. Work on the other portion of the system is under way, Petrographic identification of phases in this system is very difficult, because several of the compounds have nearly the same indices of refraction and are isotropic, or nearly so. As a result reliance was placed on identification by means of x-ray diffraction patterns; even this identification is 70n assignment from Pratt & Whitney Aircraft.
ZrF4 9t2 PERIOD ENDING JUNE 10, 7956 TEMPERATURES ARE IN OC NaF 9 98 673 were obtained fro compound, NaF*LiF*BeF,. which decomDoses to LiF and 2NaF.LiF-2BeF above aboit 24OOC (ref. 8), and another subsoldus compound, probably el?mfmtpmt ORNL-LR-OWG 44630 RbF 790 *We Jahn, Z. anorg. u. allgem Chem. 276, 113427 (1954). 87
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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
Page 21 and 22: head which are bounded by various t
Page 23 and 24: h bd * W - EcBRc+ ORNL-LR-DWG I4918
Page 25 and 26: PERIOD ENDlNC JUNE 10. 1956 TABLE 1
Page 27 and 28: ENRICHER ACTUATOR J. M. Eastman Spe
Page 29 and 30: hd - Thus, even with an input signa
Page 31 and 32: - . 140 120 p 100 g d 80 8 L s In y
Page 33 and 34: 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: - 0 e 4 000 900 800 5 700 I- a a W
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 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
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Fig.3.1.3. Region of Maximum Attack
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(d . terminated after 1217 and 1339
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- . LJ BRAZING ALLOYS IN LIQUID MET
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PERIOD ENDING JUNE 10, 1956 NaK wer
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I PERIOD ENDING JUNE 10, 1956 I Fig
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0. PERIOD ENDING JUNE 10, 1956 Fig.
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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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