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ANP PROJECT PROGRESS REPORT THE SYSTEM RLF-UF, H. A, Friedman R. E. Moore The system RbF-UF, has been investigated recently because of its importance in the qua- ternary fuel fystem NaF-RbF-ZrF,-UF,. The earlier work of Blakely et aL3 has been largely confirmed by thermal analyses of slowly cooled melts. In addition to the compounds originally reported, however, there is an incongruent compound 7RbF-6UF4. Quenching experiments on the system are now under way, but the work is not yet far enough advanced to warrant presenting a phase diagram of the system, Petrographic examinations of a series of quenched samples containing 33.3 mole % UF, indicated that a rapid inversion of the compound 2RbF*UF, occurs at some temperature below 572°C. The congruent melting point of RbF*UF, (727OC) was confirmed by petrographic examination of a series of gradient-quenched samples containing 50 mole % UF,. The composition of an incongruent compound previously thought to be RbFJUF, has now been established as RbF*3UF4 by the observation of single-phase material in a series of equilibrated and quenched samples containing 75 mole % UF,. This phase is not stable above 714OC. In mixtures Con- taining between 50 and 100 mole % UF, two phases, in addition to RbF4UF4, have been observed in both slowly cooled and quenched samples. One phase contains more than 80 mole % UF ,while the other phase contains between 50 and166.7 mole % UF,. THE SYSTEM RLF-ZrF, R. E. Moore Several revisions have been made in the tenta- tive diagram presented previously for the RbF- ZrF, system.4 The revised diagram is given in Fig. 2.1.4. Visual observation experiments have shown that the eutectic between 2RbF*ZrF, and SRbFJZrF, contains about 42 mole % ZrF, and melts at about 41OOC. Results of quenching experiments had indicated previously that the eutectic contained 3J. P. Blakely et ale, ANP Quar. Prog. Rep. June 10. 1951, ANP-65, p 87, Fig. 4.1. A. Friedman and R. J. Sheil, ANP Qum. Prog. Rep. March 10, 1956, ORNL-2061, p 72, Fig. 4.1. 84 38 mole % ZrF, and melted at 375OC. It is now apparent that 375OC is the lowered rapid inversion temperature of 2RbF*ZrF, rather than the eutectic temperature. In the region between 37 and 44.5 mole % ZrF, 2RbF*ZrF, appears optically to be like quench growth at all temperatures above the lowered inversion temperature. This accounts for the misinterpretation of the quenching data. Petrographic examination of a series of samples containing 48.3 mole % ZrF, established that 5RbF4ZrF4 is the primary phase; the iiquidus temperature is about 396OC, and the solidus temperature is 390°C. Thus, the eutectic between 5RbF4ZrF4 and RbFOZrF, contains about 48.5 mole % ZrF, and melts at 390OC. Examinations of slowly cooled preparations have shown the existence of a compound containing more than 50 mole % ZrF,. This compound has been tentatively identified as RbF-2ZrF4 by the observation of nearly single-phase material in a series of equilibrated and quenched samples containing 66.7 mole % ZrF,. This compound melts incongruently to ZrF, and liquid at 447OC. THE SYSTEM NaF-RbF-ZrF, R. E. Cleary5 H. A. Friedman A phase diagram of the fuel solvent system NaF-RbF-ZrF,, based on thermal analysis of slowly cooled melts, differential thermal analysis, and quenching experiments, is shown in Fig. 2.1.5. Some of the compatibility triangles and quasi- binary mixtures were reported previously.6 The present status of the information on the compatibility triangles, eutectics, peritectics, and boundary curves is shown in Fig. 2.1.5. The locations of the eutectics and the exact paths of the boundary curves are not considered to be final in this diagram; they are contingent on confirmation by quenching experiments. The phase relationships of the recently dis- covered compound RbF-2ZrF4 in the ternary system have not yet been determined. The ternary compounds of the solvent system are: NaF-RbF-ZrF,, which melts congruently at 615OC; 3NaF*3RbF4ZrF4, which melts incongruently at 45OoC; and NaF*RbF.2ZrF4 which melts congruently at 4600C. A fourth ternary compound with W * 50n assignment from Pratt 8, Whitney Aircraft. 'He A. Friedman, ANP Quar. Pmg. Rep. March 10. 1956, ORNL-2061, P 72. -61 0
- 0 e 4 000 900 800 5 700 I- a a W a E 600 500 4 00 PERfOD ENDlNG JUNE 10, 1956 e3MRB3Vrat.. 300 RbF 40 20 30 40 50 60 70 80 90 ZrF, ZrF, (mole%) Fig. 2.1.4. The System RbF-ZrF,. the approximate composition 3NaFSRbF*2ZrF4 line. Under optical properties, No and NE refer may exist at high temperatures. Quenching studies to the ordinary and extraordinary indices of have not yet established temperature limits on its refraction of uniaxial crystals. The compound is stability. Preliminary quenching studies show believed to form an incomplete solid solution with that the compound 3NaF=3RbF4ZrF, elts the compound NaFeRbFQZrF,, incongruently to NaF*RbF*ZrF, and liquid optical and x-ray data for the compound are Optical data: presented in the following section. OPTICAL PROPERTIES AND X-RAY PA TT E R NS F 0 R 3Na F.3 R b F *4Zr F, R. E. Thoma H. lnsley Listed below are the identifying characteristics ZrF,, a new compound encountered dies described above, The symbol istance between reflecting planes measured in angstroms. The term !/I, refers to the relative intensity of the lines as compared with an arbitrary value of 100 for the strongest Uniaxial negative NO s= 1.436 NE sz 1.430 X-ray doto: 6.77 5 6.1 1 5.72 15 15 85
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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
Page 19 and 20: 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: - a t a w 1000 900 000 - P 700 3 2
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 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
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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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