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ANP PROJECT PROGRESS REPORT 5.3.3, and the broadening of the beam at 30 and 80 cm is shown in Figs. 5.3.4 and 5.3.5, respectively. The calculated ratio of the dose rate with the duct in place tu the dose rate with a solid lead shield can be determined if an angular distribution (COS"' 6) is assumed. If cr is the number of photons per unit area emitted in the positive direction from a plane source and (+'cosm 8 is the number emitted per unit solid angle at an angle 8 from the normal, then the dose rate (neglecting the buildup factor) on the center line at a distance z from the plane of - ORNL-LR-DWG 44897 0 a 5 a 276 2 0 3 40 n z 9 W ' D 5 W c a K W In 8 e I - 2 0 3 0 z 0 L 4 m W I- a K W : : 5 0 k 2 c 4 a 2 io-' 0 20 40 60 80 Io0 I, DISTANCE FROM LEAD SHIELD (cm) Fig. 5.3.3. Water Attenuation of Gamma-Ray Beam from the Straight-Through, Aluminum-Filled, ART North-Head Duct Mockup with a Tungsten Collar. 24 ng 10 es: 5 mo $5 "Y W gP 2 0s bw ORNL-LR-DWG emn- (4898 88 f 40-' - a0 at 2 -60 -40 -20 0 20 40 €0 y, DISTANCE FROM DUCT CENTERLINE (cm) n2 5 E2 WW mi5 E2 CY KG Bd In Fig. 5.3.4. Gamma-Ray Dose Rates 30 em Beyond Straight-Through ART North-Head Duct Mockups Filled with Air or Aluminum. 40 I Fig. 5.3.5. Gamma-Ray Dose Rate 80 em Beyond Straight-Through ART North-Head Duct Mockup Filled with Aluminum. . ? h. Y . w 6.I
i - I 1 c A e W radius a (Fig. 5.3.6) is: where a u' cosrn 0 e-@ 217p dp 2 00 R 2c 1/2 . e-*(:) RdR - R2 e-Y dy where PERIOD ENDING JUNE 10, 7956 Em+1(4 = xm J - , t = distance from source to dose-measurement Y ym+l pas i t ion n/2 2n e: z (distance from lead) plus thickness of u = jko j4=o u' cosrn 8 sin 8 de d+ lead (4.3 in.), 2m' =- m+I I p = linear absorption coefficient, pl = average linear absorption coefficient along the center line with duct in place, p2 = average linear absorption coefficient along the center line with lead in place. c = flux-to-dose conversion factor. The choice of the buildup factors B, and B2 is very uncertain. It does not matter whether B1 is These functions have been tabulated by Placzek2 for values of m up to 19. taken for aluminum or water, but, since the water If a is the radius of the duct and b is the radius of the source below the lead, then the ratio of the center-line dose rate with the duct in place to that with the solid lead shield in place is 2G. Placzek, "The Functions E (x) = e-xp~-" Jlm dpsll MT-l (n*d*)* = [ Em + 1 (CC 1') - 1 Em+l(plf) (1 + " 3Bl(plt) (1 +g2 1 (1 +$)"" 2 77
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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
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NEUTRON SHIELD MATERIAL FOR HIGH-TE
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PERIOD ENDfNG JUNE 10, 7956 Fig. 3.
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wrought plate used as base material
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J point. A mixture of 50-50 vol % L
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WELDING PROCEDURE: VERTICAL FIXED,
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4 2 t 4 2 in. t 2 WCLASSFKO ORNL-LR
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FABRICATION OF JOINTS BETWEEN PUMP
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* h WELDING PROCEDURE PERlOD ENDING
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1 1 6 in. PUMP BARREL t SECTION AA
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'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
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
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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
Page 256 and 257: ANP PROJECT PROGRESS REPORT TABLE 5
Page 258 and 259: 6 ANP PROJECT PROGRESS REPORT 2 lo7
Page 260 and 261: ANP PROJECT PROGRESS REPORT GAMMA-R
Page 264 and 265: ANP PROJECT PROGRESS REPORT A I P I
Page 266 and 267: ANP PROJECT PROGRESS REPORT SECTION
Page 268 and 269: ANP PROJECT PROGRESS REPORT .. .._
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