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ANP PROJECT PROGRESS REPORT Fig. 1.4.10. Fuel-Side Wall of Tube Removed from ORNL Fuel-toNaK Heat Exchanger ORNL No. 2, Type SHE-3, Showing Mass-Transferred Metal Particles. - 1 difficulty with cold-trap circuit plugging has been encountered with any of these cold traps during routine loop operation after initial heatup by the procedure described here. In all cases, the cold traps have been capable of reducing the NaK contamination level of a 77-gal NaK system to less than 100 ppm and, in several instances, to below 50 ppm, as determined by a plugging indicator. All cold traps tested on 18-gal NaK systems have been capable of reducing the contamination to below 50 ppm and, in most cases, to blow the sensitivity of the plugging indicator (
LJ 0.005 in. on the diameter and a 30-deg conical 8 bevel was ground on the seat ring. The valve was tested for seat leakage at 1200OF in the fuel mixture (No. 30) NaF-ZrF,-UF, (50-46-4 * mole X). The minimum leakage rate obtained was 2.13 cm3/hr, with a Jpsig differential pressure across the seat and a valve stem thrust of 1200-lb force, which gave an estimated seating pressure of 12,000 psi. Failure of the seat ring braze occurred when the valve was opened after having been closed for 72 hr with the above mentioned force applied to the stem. Examination of the seat ring and plug revealed that self-welding had d occurred, and the seat ring had pulled from the valve at the brazed joint. The brazing technique has been revised for future valve fabrication. There was no evidence of galling of the stem 7 guides, such as that which occurred in the tests of prototype valve No. 1. Prototype valve No. 3 has been received from the manufacturer for testing. The flame plating on the stem cracked during a stress-relief operation, and the leakage past the seat, as measured with helium, increased. The valve will be accepted, i however, for seat material testing. 1 I * 5 Cold Trap and Plugging Indicator R. 0. Peak” The cold-trap evaluation test stand, previously described, ’ 8 has been operated only intermittently because of continual equipment difficulties. Two different types of plugging indicators were tested, and the results correlated poorly with the data PERIOD ENDING JUNE 10, 1956 Zirconium Fluoride Vapor Trap U H. CooperZo The program for the development of a trap for zirconium fluoride vapor has included an investigation of high-temperature adsorbents for ZrF, a determination of the plugging temperature of ZrF, in helium in equilibrium with the fuel as a function of the fuel temperature, and the testing of prototype traps. High-temperature adsorbents were tested by passing helium partially saturated with ZrF, through a I-in.-dia pipe packed for 24 in. with the test material. The temperature of the test section was controlled by clamshell heaters. From the trap, the hblium flowed first through water bottles to collect any residual ZrF,, through wet-test gas meters, and then to the atmosphere. The results of these tests are summarized in Table 1.4.5. Alumina is the most promising adsorbent tested, while UF, which has not yet been tested, may also prove satisfactory, since ZrF, and UF, form a solid solution with a high melting point. Charcoal, when used in a trap, enhanced the formation of ZrF, nuclei, which grew into large individual crystals. Charcoal thus may be a suitable packing for a thermal trap, since the formation of individual crystals does not plug the trap. Suitable operating conditions have not yet been established for charcoal traps. The saturation temperature of ZrF, in helium in equilibrium must be known in order to design the fuel off-gas system of the ART for temperatures which will prevent the precipitation of ZrF!. A schematic drawing of apparatus for determining the plugging temperature of tF, in ng through &-in. tubing is shown in . In each run, helium was bubbled molten fuel mixture at a measured and the helium became saturated with helium and ZrF, vapor then passed $-in.-dia tubing extending center of a stainless sfeel block which was 6 in. in diameter and 10 in. long. The entrance face of stainkss iacket was , first precipitated ing temperature of temperature. The Qwr. Prog. Rep. Sepi. 10, 1955, ORNL-1947, p 1%. 200n assignment from Pratt 8, Whitney Aircraft. 63
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: L 0 _, I, -* t; - PERIOD ENDING JUN
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
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
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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
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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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