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ANP PROJECT PROGRESS REPORT RADIATION HEATING ON THE ART EQUATORIAL PLANE IN THE VICINITY OF THE FUEL-TO-NaK HEAT EXCHANGER H. W. Bertini The results of calculations of the radiation heating on the ART equatorial plane in the outer 3 cm of the beryllium reflector and in the Inconel and the boron-containing shells on both sides of the fuel-to-NaK heat exchanger are presented in Figs. 1.2.1 and 1.2.2. The total gamma-ray heating in each region is given in Fig. 1.2.1, as well as the heating from the sources which are the main contributors to the total in each 28 Source No. 1* 2 3 4 5 6 7 8 9 10 11 12 13 14 1.2. ART PHYSICS A. M. Perry shell. The encircled numbers on Fig. 1.2.1 refer to the sources described in Table 1.2.1. The data on heating in the copper-boron layer by alpha particles from the B10(n,u)Li7 reaction are plotted in Fig. 1.2.2. The heating goes to infinity at the face of the layer closest to the core because the heating at various points is governed by an E, function, where h is the mean free path. The integral under the curve will be finite. TABLE 1.2.1. SOURCES OF RADIATION HEATING CONSIDERED IN CALCULATING THE RESULTS PRESENTED IN FIG. 1.2.1 Source Prompt gamma rays in the fuel region of the core of the reactor Decay gamma rays in the fuel region of the core of the reactor Gamma rays from inelastic scattering of neutrons in the fuel region of the core Capture gamma rays in the outer core shell Capture gamma rays in the reflector (average) Capture gamma rays in first Inconel shell outside of beryl1 ium reflector Boron capture gamma rays in copper-boron layer Alpha particles from the B1O(np)Li7 reaction in the copper-boron layer (average) Decay gamma radiation from the fuel in the heat exchanger Gamma rays from inelastic scattering of neutrons in first 9 cm of reflector (average) Capture gamma rays from delayed neutrons in the heat exchanger and Inconel shells (including the pressure shell) Capture gamma rays in the copper of the capper-boron layer Gamma rays from inelastic scattering in both core shells Capture gamma rays in the island core shell *In Fig. 1.2.1 the data for heating from sources I, 2, 3 are combined and labeled a. Source Strength 28.3 w/cm3 6.84 w/cm3 10.1 w/cm3 41.4 w/cm2 -0.5 w/cm3 22.5 w/cm3 1.8 w/cm2 42 w/cm3 2.3 w/cm3 0.7 w/cm3 ~0.1 w/cm’ OS w/cm2 -4 w/cm2 41.4 w/cm2 cs e .
62 CALCULATED HEATING (w/crn3) N w 0 VI a -d OD (D ij 0 A P P 3 3 Y -. 0 2. a to a I, r ID t ct I P cn d & VI -d 2 r m r I l In v) cn m -I HEAT EXCHANGER m r c m n r 0 D lJ E ? G 2 I I I I INCONEL CHANNEL I I I ' I ? INCONEL I m X n r 0 a to ID - 0 a BORON CARBIDE I I, F n rn 3 7. 0 P c 0.953 i T N v1 1 0 - - W 0 a ID 0 3 -k i PRESSURE SHELL ID & io 1 - 1 9561 '01 3Nnr 3NItlN3 001W3d
Page 3 and 4: Part 1 AIRCRAFT REACTOR ENGINEERING
Page 5 and 6: STATUS OF ART DESIGN Design work on
Page 7 and 8: of pressure loads. The idealized mo
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: TABLE 1.1.1. NaK PUMP SPEEDS AND HO
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
Page 59 and 60: PERIOD ENDING JUNE 10, 1956 Fig. 1.
Page 61 and 62: ART OPERATING MANUAL W. B. Cottrell
Page 63 and 64: Part 2 CHEMISTRY W. R. Grimes
Page 65 and 66:
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
Page 123 and 124:
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
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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