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ANP PROJECT PROGRESS REPORT It was also found that the silicon content had dropped to about one-third its normal value (5%) in the depleted area. Evidence of the time de- pendence of the amount of depletion is presented in Fig. 3.2.4. None of the buttons tested showed attack to a depth of more than 0.5 mil. Hardness measurements on the interior of the Fig. 3.2.3. Typical Crack Found in an lnconel Joint Brazed with the 70% Ni-13% Ge-11% CrdX Si Brazing Alloy After Exposure for 500 hr to NaK at 15006F in an lnconel Thermal-Convection Loop. Etched with 10% oxalic acid. 1OOX. Reduced 29%. 144 Sample button exposed to NaK for 350 hr gave a value of 716 DPH, while measurements at the edge gave a value of 145 DPH, as shown in Fig. 3.2.5. The buttons tested in the fuel mixture gave similar hardness traverse results. Chemical analysis of the fuel mizture from the 500-hr test and of the NaK used in the 100-hr test showed significant concentrations of boron. NIOBIUM IN STATIC SODIUM D. H. Jansen Specimens of niobium were tested in static sodium at l5OOoF for a period of lo00 hr to de- termine the suitability of liquid sodium as a pro- tective environment for niobium during high- temperature mechanical property tests. The tests were designed to show whether the niobium would be corroded by the sodium and whether the hardness of the niobium would be appreciably altered through the pickup of oxygen from the sodium. The specimens were contained in type 304 stainless steel and lnconel capsules, and the variables such as the volume of the bath, the container size, and’ the area of the specimen were adjusted to obtain a surface-area-to-volume ratio that would be as close as possible to that found in creep-test equipment. Cold traps were utilized on the bottom of each capsule to reduce the amount of oxygen in the sodium bath. The niobium specimen tested in the type 304 stainless steel capsule showed more evidence of surface roughening than did the specimen tested in the lnconel capsule, Fig. 3.2.6, and the thickness loss was also more than that of the specimen tested in the lnconel capsule, Table 3.2.3. A thin, brittle layer, approximately TABLE 3.23. RESULTS OF TESTS OF NIOBIUM IN STATIC SODIUM Exposue time: 1000 hr Temperature of sodium: 1500°F Hardness Thickness Loss Impurity Analysis of Somple (ppm) (VHN) (mils) H2 02 N2 I C As-rece ived material 130.5 2.4 40 125 300 Specimen tested in type 304 135.0 3.0 3.8 84 250 370 stainless steel tube Specimen tested in Inconel 116.4 1.8 3.4 90 92 1180 tube L4
I PERIOD ENDING JUNE 10, 1956 I Fig. 3.2.4. Specimens of Coast Metals Brazing Alloy No. 52 (89% Ni-5% Si-4% B-2% Fe) After Ex- posure in Seesaw Apparatus to the Fuel Mixture (No. 44) NaF-ZrF4-UF, (53.540-6.5 mole %) for (a) 100 hr and (b) 500 hr. 150X. Reduced 12.5%. ( . Fig. 3.2.5. Specimen of Coast Metals Brazing Alloy No. 52 (89% Ni4% Si-4% 8-256 Fe) After Ex= posure in Seesaw Apparatus to NaK for 350 hr. acid. 150X. Note differences in hardness. Etched with 10% oxalic 145
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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
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 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: PERIOD ENDING JUNE 10, 1956 NaK wer
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 (/*-
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,
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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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