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ANP PROJECT PROGRESS REPORT air and the fuel mixture seem to be surface active. Air, of course, produces an oxide film which is ever present, and the fuel mixture, in effect, creates a very thin surface film by leaching one of the alloy constituents and producing another phase on the surface, as shown in Figs. 35.6 and 3.5.7. SHORT-TIME HIGH-TEMPERATURE TENSILE PROPERTIES OF HASTELLOY B C. R. Kennedy The short-time high-temperature tensile properties of solution-annealed Hastelloy B are illustrated in Fig. 3.5.8, which gives the yield and ultimate strengths and the final elongations in the temperature range 1000 to 1800'F. As may be seen there is a distinct decrease in the final elongation and in the ultimate strength at temperatures around 1200OF. This change in properties occurs in the temperature range in which the type of fracture transforms from predominantly transgranular to intergranular. . It is interesting to note that the change in the yield strength with temperature is relatively sma I I. CR E E P-RU PTUR E PROP E R TI E S u OF HASTELLOY W C. R. Kennedy Creep testing of Hastelloy W is now in progress, and design data are presented in Figs. 3.5.9, 3.5.10, and 3.5.1 1 for solution-onnealed sheet tested in argon at 1300, 1500, and 1650OF. Hastelloy W, which has almost the same compo- sition as Hastelloy 8, except for the addition of 5% chromium and the deletion of 3% molybdenum, has creep properties very similar to those of Hastelloy B. Although Hastelloy W exhibits less of a tendency to age than Hastelloy 0, as shown in Figs. 3.5.12 and 3.5.13, a decrease in ductility occurs at 130O0F. This is also shown in Fig. 3.5.9, in which the absence of a 10% curve indi- cates that the total strain at rupture was less than 10%. Rupture points obtained from tests with the fuel mixture (No. 30) NaF-ZrF,UF, (50464 mole %) are also shown in Figs. 35.9 and 3.5.10. The times to 0.5, 1, 2, 5, and 10% total strain are identical for the same stress and temperature, and, as shown, only the rupture life is affected by Fig. 35.6. Surface Effect on the Unstressed Portion of a Hastelloy B Specimen After Exposure to the Fuel Mixture (No. 30) NaF-ZrF,-UF, (50-46-4 mole X) for 1700 hr. 1OOOX. (F * I 'W 2 04
Fig. 35.7. Surface Effect on the Stressed Portion of a Hastelloy B Specimen After Exposure to the Fuel Mixture (No. 30) NaF-ZrF,-UF, (50-46-4 mole %) for 1700 hr at a Stress of 13,500 psi. 1OOOX. (P - 1 20,ooc 1oo,oG€ 80,000 .- u) 3 m 8 60,000 io00 1400 1600 TEMPERATURE (OF) UNCLPSSlFlED ORNL-LR-DWG 1473 Fig. 3.5.8. Short-Time Tknsile Data for Solution-Annealed Hastelloy B Tested in the Temperature Range 1000 to 1800°F. 60 0 0 2 05
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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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u the salt-metal interface, and the
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of this reaction will be made at th
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+- + z 6 e 6 5 3 3 > k i m 3 2 2 1
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FeF,. The FeF, saturation points we
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UNIF, = yN should be unity (a pure
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Although it appears that the solubi
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, . 2.3. PHYSICAL PROPERTIES OF MOL
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-0 a rn u) u) DO2 oot c ;o rn OS g
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IL, - PERIOD ENDING JUNE 70, 7956 O
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8 00 700 600 - 0 0, w 500 a 3 I- U
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supporting plaque is loaded into th
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u 2.4. PRODUCTION OF FUELS c G. J.
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half of fiscal year 1957. This esti
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2.5. COMPATIBILITY OF MATERIALS AT
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volume of 1 M tartaric acid solutio
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After the trap has been opened, bot
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\ Part 3 METALLURGY W. D. Manly
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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.
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
Page 187 and 188: EFFECTOF ENVIRONMENTONCREEP- RUPTUR
Page 189: PERIOD ENDING JUNE 10, 1956 UNCLASS
Page 193 and 194: 44,000 42,000 40,000 - ._ (D 8000 v
Page 195 and 196: \:r 1 U UNCL 1158 W ioo,ooo 80,000
Page 197 and 198: fuel mixture (No. 30) NaF-ZrF -UF,
Page 199 and 200: i u * ‘*$ , .\. The Lindsay Chemi
Page 201 and 202: 6, * c L . c e 4 gi depths greater
Page 203 and 204: i 4 Part 4 HEAT TRANSFER AND PHYSIC
Page 205 and 206: 4.1. HEAT TRANSFER AND PHYSICAL PRO
Page 207 and 208: This relationship gives the ratio o
Page 209 and 210: The parameters of the’experiment
Page 211 and 212: t Fig. 4.1.7. Fuel Annulus of the V
Page 213 and 214: uncooled wall temperature that woul
Page 215 and 216: SHIELD MOCKUP REACTOR STUDY L. C. P
Page 217 and 218: Liquid (688 to 8986C) I . HT - H3Q
Page 219 and 220: THERMAL CONDUCTIVITY W. D. Powers T
Page 221 and 222: cd Fig.4.2.4. Slingers from MTR In-
Page 223 and 224: a plug when they came in contact wi
Page 225 and 226: couples were used on this loop to e
Page 227 and 228: 0 20 40 60 80 lo0 I20 440 (60 180 2
Page 229 and 230: "fast" neutron in a graphite reacto
Page 231 and 232: eached thermal equilibrium in an in
Page 233 and 234: 0.5 0.4 - a3 l- W z 0.2 0.1 UNCLASS
Page 235 and 236: TABLE 4.2.3. RESULTS OF EXAMINATION
Page 237 and 238: U could be evacuated was used for t
Page 239 and 240: ! 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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