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ANP PROJECT PROGRESS REPORT of the six types of B,C are presented in Table 4.2.2, and the results of examinations of 20 irradiated samples of the six types are given in Table 4.2.3. The four types of B,C irradiated during this quarter are described below: 1. The Norton Company supplied low-density, high-purity samples that had been hot-pressed from 325 mesh, and finer, powder and fired at above 2000%. The boron content of this material was 62.4 f 0.4 wt %. These bodies were hard, strong, and impervious. 2. The Norton Company also supplied low- density, technical-grade samples that had been hot-pressed from a-mesh, and finer, material and fired at above 2oooOC. These bodies were hard, strong, and nearly impervious, and they contained 62.4 f 0.4 wt % boron. 3. The Carborundum Company supplied tiles (No. 1) cast from a basic mixture of 90% B,C grains and 10% 200-mesh silicon metal. The cast bodies were fired at 13500C and refired at 200OOC. They were porous and friable, and they contained 64.7 f 0.5 wt 7% boron. 4. The Carborundum Company also supplied tiles (No. 2) cast from a basic mixture of 80% B,C, 10% 200-mesh, and finer, boron-metal powder, and 10% 200-mesh, and finer, silicon-metal powder. The cast bodies were fired at 1350°C and refired at 2oooOC. They were porous and friable, and they contained 67.8 f 0.4 wt 94 boron. The samples were exposed for 800 hr in the LlTR in a thermal flux of 2 x 1013 nv. The sample temperature was less than 200OC, and the total dose received by each sample was 6 x 1019 nvt (thermal). These conditions are to be compared with those expected in the ART in which the temperature of the B,C layer will be 14500F and the integrated neutron flux dosage for 500 hr of operation will be 1.2 x lot9 nvt (exposure behind a 0.030-in. gap in the cermet layer). The average burnup of these samples was 2.9%, and most of the burnup occurred in the first few thousandths of an inch of the surface layer. A much greater exposure will be required to simulate the ART operating conditions for the copper-B4C cermet layer and the boron steel, and therefore these materials will be irradiated at the MTR at a temperature of 16oOOF. Calculations indicate that these samples should receive total doses of 1.5 x lo2' nvt for the cermet and 8 x 1019 nvt for the boron steel, which are equivalent to TABLE 4.2.2. RESULTS OF SPECTROGRAPHIC ANALYSES OF B4C SAMPLES ~~ Composition (%) Norton Norton Norton Carborundum Corborundum Carborundum Element* High-Density Low-Density Low-Density Sample Cast Tile No. 1 Tile No. 2 Refired at Hot-Pressed Technical-Grade High-Purity and Bonded Refired at Sample Sample Sample with Sic 20000c 20oooc AI 0.01 -0.1 1-10 0.1-1 0.1 -1 0.1-1 0.1 -1 Ca 0.001 -0.01 0.001 -0.01 0.001 -0.01 0.001-0.01 0.001-0.01 0.001-0.01 Cr ** ** ** 0.01-0.1 0.01 -0.1 0.01 -0.1 cu ** 0.01 -0.1 ** ** ** ** Fe 0.01-0.1 0.1-1 0.1-1 1-10 0.1-1 1-10 Mg 0.0001-0.001 0.001 -0.01 0.0001 -0.001 0.001 -0.01 0.001-0.01 0.001 -0.01 Mn ** 0.01 -0.1 ** 0.0 1-0.1 0.01 -0.1 0.01 -0.1 Ni ** ** ** 0.1-1 0.01 -0.1 0.01-0.1 Ti ** 0.1-1 0.1-1 0.1-1 0.1-1 0.1-1 Zr ** 0.1-1 0.1-1 1-10 1-10 1-10 *Limit of detection: Cr, 0.004%; Cu, O.&Ol%; Mn, 0.001%; Ni, 0.02%; Ti, 0.04%; a, 0.03%. **Sought but not found. I f G .
TABLE 4.2.3. RESULTS OF EXAMINATION OF IRRADIATED B4C SAMPLES PERIOD ENDING JUNE 70, 7956 Bulk Density Dimensional Specimens Gas Appearance Change Change E vo I uti on * Change (dcm 3 1 (indin.) 3 Three Norton Co. high-density O k 0.1 crn (2.49 g/cm 3 ) hot-pressed samples 3 Three Norton Co. low-density O f 0.1 cm (2.02 g/cm3)** technical-grade samp I e s 3 Three Norton Co. low-density O k 0.1 cm (2.17 g/cm3) high-purity samples Three Carborundum Co. samples 8.1 cm3/g (0.1 cast and bonded with Sic 3 Two samples of Carborundum Co. O f 0.1 cm tile No. 1 refired to 20OO0C Six samples of Carborundum Co. None tile No. 2 refired to 20OO0C 3 *Theoretical production, approximately 1 cm . **Bulk density; sample slightly porous. None None None None, black deposit on contai ner None None 0 f 0.01 0 f 0.001 O f 1 0 * 0.001 0 * 0.05 0 f 0.001 Carborundum samples too porous and friable for precise density or dimensional measurements two weeks and one week, respectively, in the irradiated in the LlTR at 1300, 1600, and 1700°F. MTR at a thermal flux at 1.5 x 1014 nv. The samples will be checked for dimensional Irradiations have been initiated on a 7.6% stability and hardness. CaB6-92.4% Fe plate clad with stainless steel. -- --_ THE EFFECT OF RADIATION ON POLYMERS Studies of a 10.3% BN-89.7% Ni plate clad with type 304 stainless steel are planned. 0. S’ I sman IRRADIATIONS OF STRESSED SHIELDING W. W. Parkinson W. C. Sears MATERIALS There has been a continuing program in the W. J. C. Wilson E. Brundage W. W. Davis Solid State Division to study the effects of highenergy radiation on plastics and elastomers. This work has heretofore been reported only in the A test apparatus has been designed for irradiation Solid State Division progress reports, but because of a 1 wt % boron (B’*)-stoinless steel oyunder of increasing interest in this work in connection stress in the LlTR at 1300 and 1600’ In these with allied ANP projects and because there is an tests one sample will be irradiated while stressed creasing need for radiation-damage data on in compression at 500 psi at each temperature, and ganic materials, some of the current polymer one sample will be stressed similarly at the lower rk will now also be presented in the ANP temperature out of the reactor. One unstressed specimen will also be irradiated at each temperature. The irradiation periods will be three to six nd elastomers have been studied , and some of the chemical reweeks. The data obtained will be compared with en identified which cause the available data on MTR irradiations of boron- been observed in the physical stainless steel alloys for Westinghouse (WAPD). properties of irradiated polymers. A study is Specimens of an austenitic-stainless-steel-clad currently under way of the reaction products of copper-B4C cermet (6.6 wt % B4C) are also to be irradiated polymers. A summary of this work, for 249
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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
Page 183 and 184: LJ . t L t * I LJ Fig. 3.4.33. Tube
Page 185 and 186: Fig. 3.4.37. Inner Surface of Tube
Page 187 and 188: 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
Page 193 and 194: 44,000 42,000 40,000 - ._ (D 8000 v
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: 0.5 0.4 - a3 l- W z 0.2 0.1 UNCLASS
Page 237 and 238: U could be evacuated was used for t
Page 239 and 240: ! j * . x - iu I PERlOD ENDlNG JUNE
Page 241 and 242: CRITICAL EXPERIMENTS FOR THE COMPAC
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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