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ANP PROJECT PROGRESS REPORT TABLE 1.4.5. SUMMARY OF TESTS OF ZrF, ADSORBENTS Fuel Trap He1 i um Weight of Zr Adsorbent Material Temperature (OF1 Temperature (OF) Flow Rate tfps) Hours operated Not Trapped (ma) Gmme n t s Na F 1300 1300 1320 1400 to 80d 1200 to SOP A1203 1320 1400 1400 1400 to SO@ CaC12 1315 1285 to 1335 Charcoal 1315 1385 to 1419 1308 to 132lC 1110 to 116F uTemperature gradient along the trap. bHours operated as of May 15, 1956. CTemperature variations during test. 0.0573 26 0 5 0.105 119 5 0.214 98 67.1 0.0520 96 18.4 0.09 10 112 0.0568 96 28.4 0.0930 112 46.0 0.098 480b 0.0978 40 experimental plugging temperatures obtained as a function of fuel temperature, as well as the saturation temperatures predicted from both ORNL and Battelle Memorial Institute vapor pressure data, are given in Fig. 1.4.12. The experimental plugging temperatures agree to within 5% with the temperatures predicted from the vapor-pressure data. The experimental plugging temperatures and the predicted temperatures differ because the he1 ium was not actually saturated with ZrF, in the experiments. Two prototype vapor traps, of the type described previously,21 have been tested. Prototype trap No. 2, which was connected to the fuel pump of intermediate heat exchanger test stand B and was cooled by natural convection and radiation, plugged 21J. J. Milich and J. W. Kingsley, ANP Qua?. hog. Rep. Dec. 10, 1955, ORNL-2012, p 60. 64 0.0978 40 62 0.0978 66 703 0.0978 96.4 1496 NaF pellets melted in front part of trap because of formation of ZrF4-NaF eutectic NaF pellets melted in inlet section; contents of water trap of second run lost because of leak in water trap Plug in off-gas line believed to be AlF3 from HF reaction with AI2O3; water found in helium supply during this run Still in operation; no sign of plugging GCI2 melted and hence is un- satisfactory Inspection of trap showed hat ZrF, had precipitated in large individual crystals; plugs formed in off-gas line from trap in oll tests with entrained fuel after 12 hr of operation. The pump off-gas line had been installed to closely approximate one designed for the ART. The fuel entrainment indicated the need for redesign of the off-gas line. Prototype trap No. 3, which is water cooled and mounted on a fuel sump through which helium is bubbled, was placed in operation on April 27. The pressure required to maintain the helium flow at 3.0 litershin increased from 3.0 psi to 5.0 psi in 50 hr. There was no further rise in the pressure required to maintain the flow until the test was terminated after 420 hr. Two layers of ZrF, were found in the trap entrance just up- L stream of the tribe header. The first layer was rather dense and amorphous, and the second layer was more porous and crystalline. A total of 984 g . of ZrF, was found in the layers, which totaled * *
I 3 -I W CALROD HEATER 1500 I 1400 r yi‘ N 8 1300 W 2 a E 9 1200 J ($00 6‘ CALROD HEATER ZrF4-CONTAINING MIXTURE Fig. 1.4.11. Apparatus for ZrF, Tube Plugging Test. emes59 ORNL-LR-DWG 14960 I000 IO00 1100 1200 1300 1400 1500 I( FUEL TEMPERATURE PF) 1.4.12. Plugging Temperature of ZrF, Helium as a Function of Fuel Mixture Temperatu 0 PERIOD ENDlNG JUNE 10, 1956 STAINLESS STEEL JACKET UNCLASSlFlEO ORNL-LR-DWG $4959 -TO WET-TEST GAS METER 2% in. in thickness. The weight of ZrF, was only 30% of the amount that would have vaporized if the helium had been saturated with ZrF,. The dense deposit found in this trap near the inlet renders the design unsuitable for the ART. OUTER CORE SHELL THERMAL STABILITY TEST -scale model of because a sodium leak developed in the loop piping near the-test piece. It was decided to partially examine the shell before continuing the test. The center island was cut loose and lifted out of the housing assembly to expose the inner surface of the shell for inspection. A dye check of the inner 65
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 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: LJ 0.005 in. on the diameter and a
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
Page 67 and 68: - 0 Q 3 G 4000 900 800 700 a w a 5
Page 69 and 70: - a t a w 1000 900 000 - P 700 3 2
Page 71 and 72: - 0 e 4 000 900 800 5 700 I- a a W
Page 73 and 74: ZrF4 9t2 PERIOD ENDING JUNE 10, 795
Page 75 and 76: U c * NaF*BeF2-2NaF*BeF2 triangle c
Page 77 and 78: THE SYSTEM MgF2-CaF2 L. M. Bratcher
Page 79 and 80: 2.2. CHEMICAL REACTIONS IN MOLTEN S
Page 81 and 82: I id PERIOD ENDING JUNE 10, 1956 an
Page 83 and 84: PERIOD ENDlNG JUNE 10, 1956 V which
Page 85 and 86: u the salt-metal interface, and the
Page 87 and 88: of this reaction will be made at th
Page 89 and 90: +- + z 6 e 6 5 3 3 > k i m 3 2 2 1
Page 91 and 92: FeF,. The FeF, saturation points we
Page 93 and 94: UNIF, = yN should be unity (a pure
Page 95 and 96: Although it appears that the solubi
Page 97 and 98: , . 2.3. PHYSICAL PROPERTIES OF MOL
Page 99 and 100: -0 a rn u) u) DO2 oot c ;o rn OS g
Page 101 and 102:
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
Page 179 and 180:
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
Page 209 and 210:
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,
Page 247:
I, . R t 3 4 . C 7 6 5 W 5 a c3 E4
Page 250 and 251:
1 a
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ANP PROJECT PROGRESS REPORT ot(E) =
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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
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ANP PROJECT PROGRESS REPORT 5.3.3,
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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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