ORNL-2106 - the Molten Salt Energy Technologies Web Site

More documents

Recommendations

Info

ANP PROJECT PROGRESS REPORT INLET MIXING CHAMBER\ HEATER\ /INCONEL TEST SECTION BEAM SUPPORT WEIGH BEAM I MICROFORMER Fig. 4.1.12. System for Thermal Cycling of lnconel Tubing in o Fuel Environment. temperature fluctuations as the fluid moves down- stream. Effects of the thermal cycling will be determined by metallographic examination of the lnconel surface subsequent to the test. The heater and the test section are fabricated from a single 10-in. length of lnconel tubing (kin* OD, OJ35in. wall). The heater comprises the first 4 in. of this tube and will be supplied with a pulsed current through a device designed to provide a range of pulse frequencies. In order that the stresses imposed on the test section will result only from the thermal cycling of the tube surface, the heater electrodes are floated in pools of molten tin to eliminate tube bending, and 228 - . ORNL-LR-OWG 14743 a bellows is provided at the outlet end of the test section to take up the over-all thermal expansion. Preliminary tests with NaN0,-NaN0,-KNO (40-7-53 wt 96) as the heated fluid were terminate d when oxidation at the electrodes resulted in loss I of power. This situation is now being corrected. The results of these first experiments for a 1 ksec power-on - ~l/-sec power-off cycle are given in Fig. 4.1.13. the amplitude of the temperature fluctuation at two points in the test section is shown as a function of the heater power. The "tailing-off" of the data at high heater powers is caused by the slow response of the measuring equipment. The cycle period will be varied in * future experiments.
SHIELD MOCKUP REACTOR STUDY L. C. Palmer A general study of the heat transfer and fluid flow characteristics of the proposed Shield Mockup Reactor (see Chap. 5.5, "Shield Mockup Reactor Design and Construction") has been initiated. An analysis of the temperature structure within the fuel elements and the coolant and a study of the pressure distribution within the core were com- UNCLASSIFIED ORNL-LR-W 14744 - o io 20 30 40 50 60 m 80 90 (00 HEATER POWER (XI .T' ' FU f ' Y Fig. 4.1.13. Temperatwe Amplitudes Observed in Preliminory Thermal-Cycling Tests of lnconel Tubing. PERIOD ENDING JUNE 10, 1956 pleted. ,The studies are being extended to other regions of the reactor. TEMPERATURE STRUCTURE IN THE REGION BEYONDTHEARTREFLECTOR H. W. Hoffman The previous calculations10 on the temperature structure in the region beyond the reflector in the ART were extended to include a recent system modification. The new system, illustrated in Fig. 4.1.14 and designated System C, differs from those previously studied (Systems A and 8)'O in that a portion of the boron carbide has been replaced by a stain les s-stee I-c lad copper-boron carbide matrix. This layer, located between the reflector and the remaining B4C, will absorb the leakage neutrons from the core and thus prevent radiation damage of the more brittle boron carbide. A detailed description of the idealized system used in this study has been presented in a separate report. Based on these idealizations the system can be analyzed by an iterative procedure to obtain both the temperature rise of the sodium and the temperature profile for the region between the sodium and fuel return streams. The heat deposition rates used in this analysis were tenta- tive upper Iirnits.12 'OH. W. Hoffman. J. L. Wantland. and C. M. CoDenhoven, ANP Quar.-Prog. Rep. March 10, 1956, ORNL- 2061, P 174. "H. W. Hoffman, Thermal Structure /or the Region Beyond the ART Reflector - Supplement I, ORNL CF-56-4-129 (April 17, 1956). 12H. W. Bertini, personal communication to H. W. Hoffman. sEGRE;L. ORNL-LA-DWG 43U5A x, x, 3 % %% xf xg xh 4 $34 x* SYSTEM C Fig. 4.1.14. Schematic Diagram of Region Beyond the ART Reflector. I 229
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 and 50:
LJ 0.005 in. on the diameter and a
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
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
Page 103 and 104:
8 00 700 600 - 0 0, w 500 a 3 I- U
Page 105 and 106:
supporting plaque is loaded into th
Page 107 and 108:
u 2.4. PRODUCTION OF FUELS c G. J.
Page 109 and 110:
half of fiscal year 1957. This esti
Page 111 and 112:
2.5. COMPATIBILITY OF MATERIALS AT
Page 113 and 114:
volume of 1 M tartaric acid solutio
Page 115 and 116:
After the trap has been opened, bot
Page 117 and 118:
\ Part 3 METALLURGY W. D. Manly
Page 119 and 120:
FLUORIDE FUEL MIXTURES IN INCONEL F
Page 121 and 122:
PERIOD ENDING JUNE 10, 1956 TABLE 3
Page 123 and 124:
Fig.3.1.3. Region of Maximum Attack
Page 125 and 126:
(d . terminated after 1217 and 1339
Page 127 and 128:
- . LJ BRAZING ALLOYS IN LIQUID MET
Page 129 and 130:
PERIOD ENDING JUNE 10, 1956 NaK wer
Page 131 and 132:
I PERIOD ENDING JUNE 10, 1956 I Fig
Page 133 and 134:
0. PERIOD ENDING JUNE 10, 1956 Fig.
Page 135 and 136:
Fig. 3.2.10. Apparatus for Studying
Page 137 and 138:
STATIC TESTS OF INCONEL CASTINGS R.
Page 139 and 140:
t (JnOOSll 3n918-3NOt IOH (JoOOSI)
Page 141 and 142:
after the l00hr test. The extent of
Page 143 and 144:
tests of the Lindsay Mix specimens,
Page 145 and 146:
LJ DEVELOPMENT OF NICKEL-MOLYBDENUM
Page 147 and 148:
LJ PERIOD ENDING JUNE 10, 1956 Fig.
Page 149 and 150:
2. Canning of the billets with '/,-
Page 151 and 152:
165 . c, e . c3 a PERIOD ENDING JUN
Page 153 and 154:
u allow the billet to start through
Page 155 and 156:
NEUTRON SHIELD MATERIAL FOR HIGH-TE
Page 157 and 158:
PERIOD ENDfNG JUNE 10, 7956 Fig. 3.
Page 159 and 160:
wrought plate used as base material
Page 161 and 162:
J point. A mixture of 50-50 vol % L
Page 163 and 164: WELDING PROCEDURE: VERTICAL FIXED,
Page 165 and 166: 4 2 t 4 2 in. t 2 WCLASSFKO ORNL-LR
Page 167 and 168: FABRICATION OF JOINTS BETWEEN PUMP
Page 169 and 170: * h WELDING PROCEDURE PERlOD ENDING
Page 171 and 172: 1 1 6 in. PUMP BARREL t SECTION AA
Page 173 and 174: '4 x 6 x 20-in. INCONEL PLATES (/*-
Page 175 and 176: UNCLASSIFIED PHOTO 17248 Fig. 3.4.1
Page 177 and 178: through the radiator by passing col
Page 179 and 180: 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: uncooled wall temperature that woul
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 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 .. .._
show all

ORNL-2106 - the Molten Salt Energy Technologies Web Site

Create successful ePaper yourself

Delete template?

Save as template?