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ANP PROJECT PROGRESS REPORT GAMMA-RAY STREAMING THROUGH THE NaK PIPES THAT PENETRATE THE ART SHIELD T. V. Blosser D. K. Trubey As reported previously, ' a mockup experiment has been initiated to investigate the increase in the dose rate outside the ART lead shield caused by gamma-ray streaming through the NaK-filled pipes that penetrate the shield. Thus far gamma- ray dose-rate measurements have been made in the water beyond straight-through penetrations, that mock up portions of the north-head ducts. In future experiments, measurements will be made beyond similar penetrations that mock up portions of the IT. V. Blossat, ANP Quar. Prog. Rep. March 10. 1956, ORNL-2061, p 249. 5.3. BULK SHIELDING FACILITY F. C. Maienschein 1.. i south-head ducts. Ducts placed through the shield at a 45-deg angle will also be investigated, and final measurements will be made on actual NaK pipe mockups. The mockup of the north-head straight-duct penetration is shown in Fig. 5.3.1. It consisted of a 3\-in.-ID lnconel pipe filled with air or aluminum turnings and surrounded by an air annulus thot simulated the insulation of the ART. The duct was housed in a watertight thin-walled (t6-in.) aluminum case. The aluminum turnings, which were pressed into the pipe to a density of 0.85 g/cm3, simulated the NaK of the ART. A tungsten collar was fitted around the top of the duct to form a step which would reduce the streaming of gamma rays through the insulation. -TUNGSTEN COLLAR seerrrr ORNL-LR-DWG 14895 Fig. 5.3.1. Mockup of the North-Head Straight-Duct Penetration of the 43-inrThick ART Lead Shield. 274 -. * I, W 1
I A c e In order to determine the magnitude of the gammaray dose rate produced by streaming through the duct, it was necessary to know the dose transmitted through the lead shield, as well as the effect of the background produced by adjacent experimental facilities. Measurements of the gamma-ray dose rates were therefore made beyond a solid lead shield in the z,y plane of the source at a distance z above the top of the lead (see Fig. 5.3.1). The experimental data (Fig. 5.3.2) are presented in terms of the ratio of the dose rate with the duct in position to the dose rate with the duct replaced by a lead plug as a function of distance from the duct center line. The ratio of the dose rate beyond a water-filled hole to that beyond the solid lead is also shown in Fig. 5.3.2. The actual ART duct mockup will consist of two concentric pipes. The inner one, which will contain the NaK, is not present in these straight-duct mockups, but it would reduce the dose by about 30%. It should also be pointed out that the lnconel pressure shell is not part of the mockup shield. If it were, the dose-rate ratios would-be higher by a factor of approximately 2 for a 1-in.-thick pressure she1 I. A ratio of the dose rate with the aluminum-filled pipe to that with the air-filled pipe was 0.86 on the center line, which is in reasonable agreement with a calculated value. In the calculation the average energy of the gamma rays was assumed to be 3.5 Mev from the composite source. The ratio was determined from the following relation: - D1 ,. = B(p)e-w , where u2 D, = dose rate with pipefilled with aluminum turnings (with tungsten collar), D2 = dose rate through empty pipe (no collar), x t length of duct (12.8 cm), p = aluminum linear absorption coefficient = PmPl pm = mass absorption coefficient (0.034) for a rays in aluminum, minum = 0.85 g/cm3, B(P) = dose rate buildup factor (1.2). Thus n - "l = 0.83 D2 PERIOD ENDlNC JUNE 70, 7956 o x TRAVERSE, z = A y TRAVERSE, c = 10 5 cm nemt ORNL-LR-OW 44896 MINUM-FILLED DUCTS TRAVERSE,TUNGSTEN COL RLlNE MEASUREMENT NO COLLAR I = (0.5 -60 40 -20 0 20 40 60 x OR y, DISTANCE FROM DUCT CENTERLINE (cm) Fig. 5.3.2. Gamma-Ray Dose Rates Beyond Straight-Thrsugh ART North-Head Duct Mockups Filled with Air or Aluminum. as compared with the experimental value of 0.86 mentioned above. It may be seen in Fig. 5.3.2 that the tungsten collar offers little attenuation to the dose along the center line of the pipe. However, the ratio of the dose rates with and without the tungsten collar and aluminum turnings, averaged over the emitted beam, was 1.76. This ratio indicates the effective- ness of the tungsten collar in this particular con- figuration only. In the ART shield design the lead shield is fol- lowed by 31.5 in. (80.0 cm) of water. The vcater attenuation of the gamma-ray beam emerging from the duct mockup (with aluminum turnings and tungsten collar) along the z axis is shown in Fig. 275
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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
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
Page 256 and 257: ANP PROJECT PROGRESS REPORT TABLE 5
Page 258 and 259: 6 ANP PROJECT PROGRESS REPORT 2 lo7
Page 262 and 263: ANP PROJECT PROGRESS REPORT 5.3.3,
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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