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ANP PROJECT PROGRESS REPORT Fig. 1.1.1. Plastic Model of ART North-Head Structure. deck and shell areas were treated as individual plate segments with assumed edge conditions, an analysis of two circular flat plates of annular shape joined by a continuous circumferential baffle (Fig. 1.1.2), and an analysis of a composite system of plates and shells to represent the primary struc- tural members, vhich was based on the require- ment that the deformations of adjoining members be matched along the various junction lines (welds). The first two analyses served to give a very crude estimate of the stress levels involved. The pur- pose of the third analysis was to determine the stresses produced in the north head due to compatibility requirements of the various segments of shells and plates subjected to a complex pattern 20 UPPER DECK / CIRCULAR PLATES/ UNCLnSSIFIED ORNL-LR- DWG 14944 PRESSURE SHELL - 4, CONTOUR I! \ I! \ LOWER DECK’ BAFFLE (CYLINDRICAL SHELL) n Fig. 1.1.2. Circular Plates with Baffle. h 4 c ,- a .
of pressure loads. The idealized model used in this calculation is shown in Fig. 1.1.3, and the net pressure loads at various points are indicated. This model represents approximately the cross section indicated in Fig. 1.1.4. It includes some of the longest spans which appear in the design, and the results obtained from this model are there- fore conservative. The configuration of Fig. 1.1.3 was analyzed by writing the deflection equation for each member in terms of its load and edge conditions and solving the resulting system of eleven simultaneous equa- tions on the Oracle. The results were obtained in terms of the moments and reactions at the joints and edges of the members. The stresses due to these loads were then computed. The largest stress, as indicated on Fig. 1.1.3, was found to be 2100 psi. Since the highest temperature which will occur in the north-head structure during full- power operation will be approximately 130O0F, this 2100-psi stress value is to be compared to I " PERIOD ENOlNC JUNE 10. 1956 the creep properties of lnconel in the fuel mixture at about 1300OF. Creep tests have indicated that the tensile stress required to produce rupture in 1000 hr at 1300°F is about 10,000 psi. The design criterion for creep which has been selected for the ART requires that the total deformation in any member not exceed 0.2% strain in 1000 hr, At 1300OF in the fuel mixture this corresponds to a tensile stress of about 2000 psi. The experimental program, designed as a check on the calculations for the north-head structure, is under way at the University of Tennessee. It is believed that the combined results of the ana- lytical studies and the model tests will reveal any defects in the proposed design. NortbHead Thermal Stress With the completion of the analysis for the mechanical stresses in the north-head structure, attention is now being directed to the determina- tion of the thermal stress distributions. For this I bmt.v. ORNL-LR-WIG 44945 Fig. 1.1.3. Idealized Configuration of North-Head Composite Structure (Section A-A of Fig. 1.1.4). \ \ 21
Page 3 and 4: Part 1 AIRCRAFT REACTOR ENGINEERING
Page 5: STATUS OF ART DESIGN Design work on
Page 9 and 10: UPPER DECK 7 @ PRESSURE SHEL PERIOD
Page 11 and 12: SOD,UM r--- INCONEL TANK ROOF 0 0.5
Page 13 and 14: TABLE 1.1.1. NaK PUMP SPEEDS AND HO
Page 15 and 16: 62 CALCULATED HEATING (w/crn3) N w
Page 17 and 18: where I = radius of source (taken a
Page 19 and 20: heat exchanger was used. The heatin
Page 21 and 22: head which are bounded by various t
Page 23 and 24: h bd * W - EcBRc+ ORNL-LR-DWG I4918
Page 25 and 26: PERIOD ENDlNC JUNE 10. 1956 TABLE 1
Page 27 and 28: ENRICHER ACTUATOR J. M. Eastman Spe
Page 29 and 30: hd - Thus, even with an input signa
Page 31 and 32: - . 140 120 p 100 g d 80 8 L s In y
Page 33 and 34: and lose their hardness in the pres
Page 35 and 36: p. W 2.5 0.5 0 400 OPERATING TIME (
Page 37 and 38: i 20 too 80 40 20 PERIOD ENDING JUN
Page 39 and 40: c' I - + r 500 450 400 3 50 300 2 2
Page 41 and 42: 01) 0V3H 5: N 0 2 s 0 0 0 5: 0 2 s
Page 43 and 44: the first 200OF and B0F/sec for the
Page 45 and 46: PERIOD ENDING JUNE 10, 1956 TABLE 1
Page 47 and 48: L 0 _, I, -* t; - PERIOD ENDING JUN
Page 49 and 50: LJ 0.005 in. on the diameter and a
Page 51 and 52: I 3 -I W CALROD HEATER 1500 I 1400
Page 53 and 54: -17 Inconel I .._I_ I" .. _ _ ~ ._
Page 55 and 56: i E ART FACILITY F. R. McQuilkin Co
Page 57 and 58:
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.
Page 135 and 136:
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
Page 191 and 192:
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
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t Fig. 4.1.7. Fuel Annulus of the V
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uncooled wall temperature that woul
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SHIELD MOCKUP REACTOR STUDY L. C. P
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Liquid (688 to 8986C) I . HT - H3Q
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THERMAL CONDUCTIVITY W. D. Powers T
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cd Fig.4.2.4. Slingers from MTR In-
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a plug when they came in contact wi
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couples were used on this loop to e
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0 20 40 60 80 lo0 I20 440 (60 180 2
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"fast" neutron in a graphite reacto
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eached thermal equilibrium in an in
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0.5 0.4 - a3 l- W z 0.2 0.1 UNCLASS
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TABLE 4.2.3. RESULTS OF EXAMINATION
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U could be evacuated was used for t
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! 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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