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ANP PROJECT PROGRESS REPORT IIOV -60- atom as it travels through the lattice result in the formation of lattice vaccncies and interstitial atoms. Since the germanium lattice is fairly open, the interstitial atoms can diffuse readily through the crystal. Because of the high dielectric constant of germanium, the interstitial atom is ionized at room temperature, and hence its diffusion should be influenced by the presence of an electric field. Fields of the order of tenths of a volt per micron are available in the barrier region of a diode, and the conductivity of the diode is extremely sensitive to changes in carrier concentration in the region of the barrier. A 1N38A point-contact germanium rectifier was exposed for 5 min in hole 51-N of the ORNL Graphite Reactor. After removal from the reactor the rectifier was biased in the forward direction 246 Fig. 4.2.16. Transistor Test Circuit. ‘0 at 0.7 v in order to remove the potential gradient in the barrier region. The measured current was low because of radiation damage. The unit was then placed in an oil bath to maintain a constant temperature of about 250C for six days. At the end of the six-day period there had been no observable change in the current passing through the sample at 0.7-v bias. The bias was removed for 2 hr, then restored. When the bias had been restored, it was noted that the current had in- creased by about an order of magnitude. After eight days in the biased condition, the current had not changed. When the bias was removed, an electric field was established at the barrier to cause the relative interstitial atoms to diffuse from the barrier region. This removal of interstitial atoms from the p-type . t
0.5 0.4 - a3 l- W z 0.2 0.1 UNCLASSIFIED ORNL-LR-DWG 44749 100 80 60 - 0 0 0 1 2 3 4 5 6 7 8 9 (0 11 12 13 14 45(x105) RADIATION DOSAGE ( r/hr ) 40 20 E I Fig. 4.2.17. Effect of Radiation on Collector Current and Amplification of a Minneapolis-Honey- well H-2 Power Transistor Irradiated in Gamma- Ray Source of 2.57 x lo5 rhr. - s I .o 0.9 0. E 0.7 2 0.6 -l 5 a5 I- z l- W 2 0.4 0.3 ~ Function of Integrated Fast-Neuiron Exposure. 2 PERlOD ENDING JUNE 10, 1956 side of the barrier results in annealing out the type of damage which tends to make the p-type side less p-type and transporting it to the n-type side. Hence both sides of the barrier are annealed toward their initial condition and the forward current increases toward its initial value. RADIATION DAMAGE TO BORON CARBIDE 0. s I man J. G. Morgan The study of radiation effects on B,C, initiated previou~ly,~~ was completed. The apparatus used for the irradiation of samples in the LlTR was described in the previous report. The first samples irradiated were hot-pressed, high-density B,C, supplied by the Norton Company, and slip-cast B,C bonded with Sic, supplied by The Carborundum Company. Four other types of B,C have now been irradiated. The results of spectrographic analyses 330. Sisman e: al.. ANP Quar. Prog. Rep. March 10, 1956, ORNL-2061, p 204. AMPLIFICAl ' ,N: A-i DROP ACROSS RESISTOR IN COLLECTOR LEG TEGRATED NEUTRON FLUX (nvt,) UNCLASSIFIED ORNL-LR-DWG 437S9 I ; / I t nneapolis-Honeywell H-2 Power 247
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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,
Page 181 and 182: 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: eached thermal equilibrium in an in
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 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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