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ANP PROJECT PROGRESS REPORT ORIGINAL GAP =0.031 in. ( x = 0.135 in.) PRESENT GAP = 0.043 in ( x 9 = 0.1875 in 220 SHELL TO REPRESENT REFLECTOR (PLEXIGLAS) OUTER CORE SHELL (14-S-T-41 ALUMINUM ALLOY) PUMP ROTAMETER -TO PUMP Fig. 4.1.1. Vertical Section Through Reflector-Core Shell Annulus Model. 9F37€+ ORNL-LR-OWG 14738 6, * . Q c a t -.
This relationship gives the ratio of the averages of the- velocities at the two stations farthest from the inlets to the averages of the velocities at the two stations nearest the inlets. The relationship for the flow distribution when only one pump was operating was defined as - - '3 pump A '1 pump B Q, V, [ operating + ] [operating] -t QtJ 2 Some of the experimental results are presented in Fig. 4.1.2 in terms of these relationships. - The predicted flow distribution in the ART system ORNL-LR-DWG (4739 f.08 I .06 OC 3 ! .04 i .02 4.00 to4 2 5 I d REYNOLDS MODULUS AT MIDPLANE Fig. Flow Distribution in Reflec e Shell Annulus. PERIOD ENOfNG JUNE 10, 1956 was obtained by extrapolating the data to the Reynolds numbers for the actual system at the mid-plane of the annulus. A summary of the results is given in Table 4.1.1. The minimum flow rate was found in the portions of the annulus nearest the inlets, while the maximum flow rate was observed in the portions farthest away. These conditions are the reverse of those anticipated, and a possible explanation is that the fluid entering the annulus from the inlet header must abruptly change direction and it probably undergoes high velocity losses, particu- larly near the inlet to the annulus where the momentum is the greatest. After the model inlet header used in these experiments had been fabri- cated, the design of the actual ART sodium system was modified so that uniform distribution of sodium flow would exist in the annulus if there were no eccentricities. The flow in such a concentric annulus will be axial; that is, there will be no spiraling, Studies of the motion pictures of the flow in the model indicated that, for a constant pump pressure, the average velocity fluctuation at any point in the annulus would probably be less than k5%. The flow distributions in the annulus for two possible conditions of eccentricity of the core shell were also studied. Buckling of the core shell between the spacers was simulated to produce a local eccentricity. Since the reduction in flow as a function of the reduction in flow area was the prime concern, the buckling of the core shell was simulated by adding pieces of tape, as shown in Fig. 4.1.3. For a local reduction in annulus thickness of 50% (t/to = 0.5), the flow from inlet to outlet through that sector of the annulus was 7% of the average flow. Radial eccentricity was also simulated to study the effect of a slight canting of the core shell on TABLE CT.1. SUMMARY OF CONCENTRIC ANNULUS FLOW DISTRIBUTION STUDIES Annulus width, In. Reynolds modulus at mid-plane 0.386 1.00 0.609 1.00 For two pumps operating 1.045 1.025 1.025 1.02 Far one pump operating (70% normal flow assumed) 1.08 1.06 1.075 1-07 221
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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.
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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
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 and 190: PERIOD ENDING JUNE 10, 1956 UNCLASS
Page 191 and 192: Fig. 35.7. Surface Effect on the St
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: 4.1. HEAT TRANSFER AND PHYSICAL PRO
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
Page 241 and 242: CRITICAL EXPERIMENTS FOR THE COMPAC
Page 243 and 244: . I) a W PERIOD ENDING JUNE 10, 195
Page 245 and 246: U I I R i c . --. in. long, 18’4,
Page 247: I, . R t 3 4 . C 7 6 5 W 5 a c3 E4
Page 250 and 251: 1 a
Page 252 and 253: ANP PROJECT PROGRESS REPORT ot(E) =
Page 254 and 255: 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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