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ANP PROJECT PROGRESS REPORT TABLE 5.21. SUMMARY OF THE CONFIGURATIONS USED FOR LTSF MOCKUP TESTS OF ADVANCED SHIELDING MATERIALS Configuration No. Cornpositlon 69-0 Pure water Transformer oil 69-1 1 ft of LiH in oil 2 ft of LiH in oil 3 ft of LiH in oil 69-2 69-6 69-7 . 4 in. of Zr in oil 4 In. of Zr + 1 ft of LiH in oil 4 in. of Zr +2 ft of LiH in oil 4 in. of Zr + 3 ft of LiH in oil 3 in. of Pb in oil 3 in. of Pb + 1 ft of LiH in oil 3 in. of Pb +2 ft of LiH in oil 3 in. of Pb +3 ft of LiH in oil 3 in. of U in oil 3 in. of U + 1 ft of LiH in oil 3 in. of U + 2 ft of LiH in oil 3 in. of U +3 ft of LiH in oil distances from the source is interpreted as an effect of photoneutron production in CI3 and deute- rium, although no quantitative analysis has been made. At smaller distances from the source, these data may be used to estimate the macroscopic removal cross section of lithium hydride at room temperature in an oil medium. A preliminary value of 0.12 cm” was obtained, which is in good agree- ment with the value expected on the basis of pre- vious removal-cross-section measurements on a lithium-metal slab.‘ The observed gamma-ray tissue doses are given in Figs. 5.2.6 through 5.2.9. It can be noted that 270 TABLE 5.22 PHYSICAL PROPERTIES OF THE SHIELDING MATERIALS TESTED Material Description Transformer oil Density, 0.87 g/cm3 at 20°C; analysis, 86.7 wt % C and 12.7 wt % H Lithium hydride* 5 x 5 x 1 ft slabs encased in AI cans ($-in.-thick walls); density, about 0.75 9/cm3; purity, about 95% Zirconium* Lead Uranium 52 X 55 x 2 in. metallic slabs 55 X 60 X 1.5 in. metallic slobs 52 x 55 x 1.5 in. depleted metallic slabs containing 0.24 wt % u235 *Raw rnateriols furnished by GE-ANPD. one slab of lithium hydride behind a heavy shielding material reduces the dose at larger distances from the source. This is interpreted as a reduction of secondary gamma-ray production caused by the presence of Li6 in the lithium hydride. The data obtained upon subsequent additions of LiH indi- cate, as expected, that LiH does not have so large a macros cop i c gamm a-ray absorption coefficient as that of the oil. It is planned to continue these studies of combi- nations of lithium hydride with other shielding materials. Attempts will also be made to obtain reliable fast-neutron measurements, where pos- sible, for the configurations already studied. 4G. T. Chapman and C. L. Storrs, Effective Neutron Removal Cross Sections for Shielding, ORNL-1843 (Aug. 31, 1955). - w* -
h . 40' ! 5 5 2 404 5 2 403 $ 2 + 2 40 z I a 5 z W E 2 2 4 6 ' 5 2 XCRev 2-04-057-69- 264 I I I 40-2 20 40 60 80 100 '420 440 460 2%. DISTANCE FROM SOURCE PLATE (em) Fig. 52.2. Thermal-Neutron Flux Traverses for Configurations 69-0 and 69-1. 2 PERIOD ENDJNG JUNE IO, 1956 &!ern 2-01 -057-69-268 I 4 I I I I I I I 10-3 0 20 40 60 80 100 120 140 160 zso, DISTANCE FROM SOURCE PLATE (Cm) Fig. 5.2.3. Thermal-Neutron Flux Traverses for Configuration 69-2. 271
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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
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
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 258 and 259: 6 ANP PROJECT PROGRESS REPORT 2 lo7
Page 260 and 261: ANP PROJECT PROGRESS REPORT GAMMA-R
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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