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ANP PROJECT PROGRESS REPORT ~ TABLE 3.24. RESULTS OF METALLOGRAPHIC EXAMINATION OF THE INTERFACES OF THE Li SPECIMENS SHOWN IN FIG. 3.213 a Test environment: sodium Test duration: 1000 hr Test temperature: 130O0F Stress on specimens: 500 psi Interface Metallographic Notas A-8:' lnconel VI beryllium - direct 10 to 24 mils of alloy formation (BeplNi5 plus BeNi) along contact interface; 4 mils of lnconel consumed in the production of reaction layer 8-C: Beryllium VI lnconel - direct 22 to 24 mils of uniform alloy formation along interface contact C-D: lnconel with 1-mil chromium 3.5 to 7 mils of alloy formation; 7-mil layer found where plate VI beryllium plating was thinnest D-E: Beryllium vs 2-mil chromium 2 mils of interaction between specimens along 90% of inter- plate on lnconel face; 6-mil layer detected at one area where plating 'See Fig. 3.2.12 for location of interface. 150 ~~ appeared to have been defective
STATIC TESTS OF INCONEL CASTINGS R. Carlander In thermal-convection loop tests bf lnconel castings in the fuel mixture (No. 30) NaF-ZrF,-UF, (50-46-4 mole %), much heavier attack of the cast material occurred than is normally observed for wrought lnconel (see Chap. 3.1, "Dynamic Cor- rosion Studies"). Metallographic examination of the as-received material showed the presence of cracks, stringer porosity, and large grains, with the grain boundaries perpendicular to the surface. In order to obtain further information on the effect of the composition of the cast material on its corrosion resistance, static tests of three lnconel castings that differed primarily in silicon content were performed in the fuel mixture (No. 30) NaF- ZrF,-UF, (50-46-4 mole %) in wrought lnconel capsules for 1000 hr ut 15OOOF. Examination of the tested specimens revealed that the casting with the highest silicon content (1.93%) was the least attacked, while the casting with the lowest silicon content was the most severely attacked. In all cases, the attack was a combination of subsurface voids and intergranular penetration. The depth of subsurface voids on the Inconel castings was 3 to 4 mils, as compared with 2 to 4 mils on the wrought lnconel capsules. The intergranular penetration, however, varied from 3 mils on the high-silicon-content casting to 12 mils on the low-silicon-content casting. This PERIOD ENDING JUNE lo, l9S6 difference is attributed to the porosity and to the grain boundaries running perpendicular to the surface of the casting. The results of metallographic examinations of the three cast specimens are presented in Table 3.2.5, and the wrought lnconel capsule and cast lnconel specimen No. 321 are shown in Fig. 3.2.14. In every case the wrought lnconel container was more corrosion resistant than was the cast lnconel specimen. INCONEL AND STAINLESS STEEL IN NaK CONTAINING LITHIUM R. Carlander Type 316 stainless steel and lnconel were exposed to NaK containing lithium in static and in dynamic systems in order to determine the effect of the lithium on corrosion resistance. In the static tests the specimens were exposed to NaK (5644 wt %) with lithium additions of 1, 5, 10, 20, and 30 wt % for 100 hr at 1500OF. No attack occurred in any of the tests. For the dynamic tests, 12-in.-long capsules were filled to 40% of their volume with NaK plus lithium (5 or 10 wt %) and placed in a tilting- type furnace (1 cpm) at a hot-zone temperature of 15OOOF (cold zone, 1100'F) for 100 hr. No mass transfer occurred in any of these systems. The lnconel exposed to NaK with 10 wt % lithium added was attacked to a depth of 1 mil in the hot tone, while the other capsules were unattacked. TABLE 3.25. RESULTS OF METALLOGRAPHIC EXAMINATION OF CAST INCONEL SPECIMENS AFTER EXPOSURE TO STATIC NaF-ZrF4-UF4 (50-46-4 mole %) FOR 1000 hr AT lSOO°F Cast Inconel Slllcon bepth of Attack (mils) Specimen Content Wrought lnconel Cast lnconel Metallographic Notes on Cost cracks apparent lnconel Specimen intergranular penetration to depth of 8 mils; no cracks apparent 151
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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
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ZrF4 9t2 PERIOD ENDING JUNE 10, 795
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U c * NaF*BeF2-2NaF*BeF2 triangle c
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THE SYSTEM MgF2-CaF2 L. M. Bratcher
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2.2. CHEMICAL REACTIONS IN MOLTEN S
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I id PERIOD ENDING JUNE 10, 1956 an
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PERIOD ENDlNG JUNE 10, 1956 V which
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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: Fig. 3.2.10. Apparatus for Studying
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 (/*-
Page 175 and 176: UNCLASSIFIED PHOTO 17248 Fig. 3.4.1
Page 177 and 178: through the radiator by passing col
Page 179 and 180: L, . 1 Q t V ERIOD ENDING JUNE 10,
Page 181 and 182: to permit the examination of indivi
Page 183 and 184: LJ . t L t * I LJ Fig. 3.4.33. Tube
Page 185 and 186: 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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