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ANP PROJECT PROGRESS REPORT and 5%, respectively. As may be seen in Table 3.1.5, the chromium content of the fuel mixture circulated in the Hastelloy X loop was much higher than that of the fuel mixture circulated in the Hastelloy W loop. This reflects the greater tendency toward chromium removal and the resultant void formation in alloys with high chromium contents, such as Hastelloy X. FLUORIDE FUEL MIXTURES IN MONEL THE RMAL-CONV ECT IO N LOOP S J. H. DeVan Three monel thermal-convection loops, 806, 808, and 809, completed 500, 545, and 1027 hr of operation, respectively, with the fuel mixture Fig. 3.1.5. Metallic Crystals and Layer De- posited in Cold Leg of Hastelloy X Thermal- Convection Loop Which Circulated the Fuel Mixture (No. 30) NaF-ZrF,-UF, (50-46-4 mole %) for 1000 hr at a Hot-Leg Temperature of l5000F. a,. 250X. Reduced 32.5%. 138 (No. 107) NaF-LiF-KF-UF, (1 1.2-41-45.3-2.5 mote %) circulating at a hot-leg temperature of 15OOoF. Loops 808 and 809, which were scheduled to operate 1000 and 1500 hr, respectively, were terminated before completion of the scheduled 5 operating period because of excessive oxidation of the outside surface of the monel tubing. The oxidation did not completely penetrate the tube wall in either loop. Metallographic examination revealed hot-leg attack to a depth of 1 mil, as shown in Fig. 3.1.6, in all these loops. Three other monel loops, 880, 881, and 882, that had been chromium-plated to provide oxidation pro- tection were operated under the same conditions, but, apparently, the platings were imperfect, and two of these three loops, 881 and 882, were Fig. 3.1.6. Region of Maximum Attack of Hot Leg of Monel Thermal-Convection Loop 809 Which Circulated the Fuel Mixture (No. 107) NaF-LiF- KF-UF, (11.2-41-453-2.5 mdle %) for 1027 hr at a Hot-Leg Temperature of 15000F. Etched with HN03-acetic acid. 250X. Reduced 32.5%. TABLE 81.5. CHEMICAL ANALYSES OF THE FUEL MIXTURE (No. 30) NoF-ZrF4-UF4 (50-46-4 mole 46) BEFORE AND AFTER CIRCULATION FOR 1000 hr AT 15OO0F IN HASTELLOY X AND W THERMAL-CONVECTION LOOPS Loop Loop Uranium Content Impurities Found (ppm) Sample Token No. Materia I (* 46) Ni Cr Fe 857 Hartalloy X Before filling 8.39 260 135 115 After draining 8.68 40 1060 125 873 Hastellay W Before filling 8.78 80 60 75 After draining 8.82 85 275 110 gi
(d . terminated after 1217 and 1339 hr of the 1500 hr schedu fed because of. excessive oxidation and resultant leaks in the heated The remaining loop, 880, compl * 1OOQ' hr of operation. Meta of these loops have not been completed, c SPECIAL FLUORIDE FUEL MIXTURES IN INCONEL THERMAL-CONVECTION LOOPS J. H. DeVan Additional lnconel thermal-convection loops have been operated to evaluate corrosion properties PERIOD ENDING JUNE 10, l956 of several special fluoride fuel mixtures. Tests of 500 hr duration were completed for mixtures in the MF-ZrF,-UF, system, where MF is KF, LiF, NaF, or RbF. Mixtures with each of these fluorides and 40 or 46 mole % ZrF, have been tested; each mixture contained 4 mole % UF,. The results obtained for the fuels sontaining 46 mole % ZrF, were reported previously,3 but they are repeated in Table 3.1.6 for comparison. Lowering the ZrF, content, as shown in Table 3.1.6, had no effect on attack by the NaF-containing mixture, but the attack by the KF- and RbF-containing mixtures increased from 1 to 2 mils. The LiF-containing TABLE 3.1.6. RESULTS OF METALLOGRAPHIC EXAMINATIONS OF INCONEL THERMAL-CONVECTION LOOPS OPERATED WITH SPECIAL FLUORIDE FUEL MIXTURES AT A HOT-LEG TEMPERATURE OF lSOO°F Loop Fuel Mixture Fuel Mixture Composition Operating Time Metal lograph ic Results Maximum Hat-Leg No. Code Designation (mole X) Attack Cold-Leg Deposits (hr) (mils) 845 94 KF-ZrF4-UF4; 50-46-4 500 846 94 K F*Zr F4-U F4; 50-46-4 500 883 94 K F-ZrF4-U F4; 50-46-4 1500 884 94 K F-Zr F4-U F4; 50-46-4 1500 ' 930 WR4 K F-Zr F4-U Fa; 54-40-4 500 931 WR4 KF-ZrF4-UF4; 56-40-4 500 847 93 L i F-Zr F4-UF4; 50-46-4 500 93 LiF*ZrF4-UF4; 50-46-4 500 WR3 WR3 95 95 R bF-Zr F4-UF4; 50-46-4 WRS WR5 30 NaF-ZrF4=UF4; 50-46-4 30 NaF-ZrF4-UF4; 50-46-4 WR2 WR2 6.5 Metallic layer 8 Metallic layer 11 ktallic layer 9 Metallic layer 7 Metallic layer 9 Metallic layer 17.5 Possible crystals 19 Possible crystals 10 Metallic layer and crystals 10 Metallic layer and crystals 9 9 Me ta I I ic layer 10 Metallic layer and crystals 11 10.5 9 10 7 ,139
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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" .. _ _ ~ ._
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i E ART FACILITY F. R. McQuilkin Co
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L7i PERIOD ENDING JUNE 10, 1956 Fig
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PERIOD ENDING JUNE 10, 1956 Fig. 1.
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ART OPERATING MANUAL W. B. Cottrell
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Part 2 CHEMISTRY W. R. Grimes
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W 2.1. PHASE EQUILIBRIUM STUDIES' C
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- 0 Q 3 G 4000 900 800 700 a w a 5
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- a t a w 1000 900 000 - P 700 3 2
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- 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 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: Fig.3.1.3. Region of Maximum Attack
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
Page 157 and 158: PERIOD ENDfNG JUNE 10, 7956 Fig. 3.
Page 159 and 160: wrought plate used as base material
Page 161 and 162: J point. A mixture of 50-50 vol % L
Page 163 and 164: WELDING PROCEDURE: VERTICAL FIXED,
Page 165 and 166: 4 2 t 4 2 in. t 2 WCLASSFKO ORNL-LR
Page 167 and 168: FABRICATION OF JOINTS BETWEEN PUMP
Page 169 and 170: * h WELDING PROCEDURE PERlOD ENDING
Page 171 and 172: 1 1 6 in. PUMP BARREL t SECTION AA
Page 173 and 174: '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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