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I I 254 1 ! A NP PROJECT PROGRESS REPORT runs was pentavalent. As a result of disprapor- These results indicate that, if a significant partionation of the pentavalent uranium in the analyti- tial pressure of UF, is retained in the NaF bed cal procedure, however, the tetravalent uranium because of a plugged line or cold trap during UF, content in each case was approximately equal to desorption, excessive UF, decomposition will octhe hexavalent content. The decomposition reac- cur when the temperature reaches the 300 to 400OC tion is therefore believed to be range. Therefore precautions must be taken to UF6*3NaF + UFpNaF i '/Fz ensure that full sweep-gas flow through the NaF bed is maintained during UF, desorption. 61 .
CRITICAL EXPERIMENTS FOR THE COMPACT-CORE REFLECTOR-MODERATER REACTOR E. Demski’ J. J. Lynn W. 3. Fader’ D. A. Harvey’ D. Scott 4.4. CRITICAL EXPERIMENTS D. E. McCarty E. V. Sandin’ The study of the NDA2-proposed, sodium-cooled, reflector-moderated reactor with solid fuel element~~ has been completed. In the critical assembly the fuel region contained 0.004-in.-thick uranium sheets interleaved between aluminum and stainless steel sheets. This fuel region was separated from the beryllium of the island and of the reflector by stainless steel shells. As described previo~sly,~ additional uranium, in the form of 0.01-in.-thick disks, was added in one section of the fuel region to provide excess reactivity for other measurements. An evaluation of the effect of this local nonuniform fuel distribution on the reactivity was made by replacing 2636 g of U235 in 0.004-in.-thick sheets with 2678 g of U235 in 0.01-in.-thick disks in another section of the core. With the other materials unchanged, there was a reactivity loss of only 19 cents. Evaluation of Stainless Steel Shell The loss in reactivity caused by the stainless steel shells was determined by substituting aluminum shells of the same dimensions, The exchange of 4.4 kg of aluminum for 11.9 kg of stainless steel resulted in a gain in reactivity of $4.20, ‘A. D. Calli hon et al., ANP Qwr. Prog. Re March 10, 1956, ORNL-2061, p 64; Dec. IO, 1955, gkNL-2012, p 73. A. D. Callihan PERIOD ENDING JUNE IO, 1956 over the 28t-in. length of the outer reflector and comprised 70% of the outer cylindrical layer resulted in a loss in reactivity of $2.39. Measurements of Gamma-Ray Heating in Beryllium Capacitive ionization chambers were used to measure the distribution of gamma-ray heating in the beryllium of the island and the reflector of the critical assembly by a method developed at the Knolls Atomic Power Laboratory.’ The chambers are constructed of beryllium and have a 10-mil- thick annular cavity T6 in. OD and s/s in. deep, The results are expressed as power dissipated as heat in a unit volume per unit reactor power. The reactor power was determined from a calibration based on the intensity of a fission-product gamma ray from an irradiated uranium foil.6 A plot of the data obtained from radial traverses C and 107 in. from the mid-plane of the reactor is ’6 given in Fig. 4.4.1. Three longitudinal traverses, one along the axis of the reactor and the others 45/16 and 73/16 in. from the‘ axis, are plotted in Fig. 4.4.2. These data have not been corrected for the ionization resulting from the (n,p) reaction in the air-filled chambers and may overestimate the heating adjacent to the fuel by as much as 25%, an estimate based on the work at KAPL. An attempt was made to measure this error by filling the chambers with CO, but it was apparent that they were not gas-tight during these experiments. It may be possible to make a correction to these data by using the results of similar measurements in another assembly. A layer of beryllium, 2% in. thick, was removed from the top of the reactor, and one traverse was repeated with this thinner reflector. The heating was observed to be unaffected in the region between the fuel and a point 3 in. from the surface of the modified reflector, In this outer 3-in. layer the heating decreased to a value, at the surface, about 35% less than it was at the same distance from the fuel in the thicker reflector. ’C. A. Rich and R. f. Slovacek, Gamma-Ray Heating Measurements in the SIR PPA-18, KAPL-866 (Jan. 7, 1953). 6S. Snyder, Absolute Determination of Power Prodwed in a Nominally Zero Power Reactor, ORNL-2068 (May 15, 1956). 255
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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
Page 189 and 190: PERIOD ENDING JUNE 10, 1956 UNCLASS
Page 191 and 192: Fig. 35.7. Surface Effect on the St
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Page 195 and 196: \:r 1 U UNCL 1158 W ioo,ooo 80,000
Page 197 and 198: fuel mixture (No. 30) NaF-ZrF -UF,
Page 199 and 200: i u * ‘*$ , .\. The Lindsay Chemi
Page 201 and 202: 6, * c L . c e 4 gi depths greater
Page 203 and 204: 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: ! j * . x - iu I PERlOD ENDlNG JUNE
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 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
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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