ORNL-2106 - the Molten Salt Energy Technologies Web Site

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ANP PROJECT PROGRESS REPORT A I P I UNCUSSIFIED ORNL-LR-QWG I4900 Fig. 5.3.6. Geometry for Calculation of Dose Rate at Distance z from Source. thickness following the lead is thin (-0.4 mfp), B, was assumed to be the buildup factor for lead. The calculated ratio is plotted as a function of the angular distribution index m in Fig. 5.3.7. There is excellent agreement with the experimental value if m is taken to be 2. This is what might be expected from a combination of an isotropic component (cadmium capture gamma rays) and a highly directional component (carbon capture and reactor LL 0 1 1 Ga o !tma&s ORNL-LR-DWG (4901 2 4 6 8 10 42 14 m, ANGULAR DISTRIBUTION INDEX Fig. 5.3.7. Calculated Ratio of Center-Line Gamma-Ray Dose Rate Beyond Straight-Through ART North-Head Duct Mockup to That Beyond Solid Lead Shield as a Function of Angular Distri- bution (cosm e) of the Source. gamma rays). Of course, the buildup factor and the monoenergetic source assumptions introduce some uncertainty. Also, both the energy spectrum and the angular distribution for the ART reactor are undoubtedly somewhat different than those for the mockup.
Lv 5.4. SHIELD MOCKUP CORE C. E. Clifford L. B. Holland PERIOD ENDING JUNE 70, 7956 Tests of optimized reactor shield desSgns are the inlet cooling line. The CFRMR has a control made, currently, with a full-scale mockup of the rod of slightly smaller diameter in this position, shield and a known source. The effectiveness of but calculations have shown that the effect of the the shield in its final application is then predicted cooling line will not be significant. The SMC will by making source corrections. To date the source be controlled by using thin, curved plates confor the shielding tests has often been a swimming- taining Blo at the outer edge of the island between pool type of reactor, but with the circulating-fuel the fuel plates and the beryllium. In the core region reflector-moderated reactor (CFRMR) now being it is proposed to use fixed fuel plates of UO, and considered for aircraft propulsion it is considerably stainless steel, which will be similar in cross more difficult to correct for the differences between section to the Army Package Power Reactor fuel the two sources. In recent months it has become plates. The shape of the plates will be peculiar apparent that a shield test with a reactor that more to the SMC. The feasibility of the shape has nearly mocks up a CFRMR is required. The construction of a 5Mw reactor that will use already been determined with test fuel plates. There will be a total of 200 vertical fuel plates fixed fuel elements which will correctly mockup'all placed radially around the beryllium island, and the radiation expected from the CFRMR designed normal water will be used as the coolant. The by Pratt & Whitney, except the decay gamma rays core region will be separated from the beryllium and rleutrons from the circulating fuel in the heat island and the reflector by lnconel shells, as reexchanger, has been proposed. A preliminary de- quired by the CFRMR. sign and a cost estimate are being prepared on The region above the CFRMR reactor core will which to base a formal construction proposal. The be difficult to mock up. Since it constitutes a reactorwill be called the Shield Mockup Core (SMC) small total angle,, it seems best, in the SMC, to and will be used with the latest optimized shield attempt to black out radiation from this region. at the Tower Shielding Facility (TSF) to determine Another feature in favor of this idea is that the whether the calculated dose in the crew comport- control-rod drives and controlshamber leads will ment agrees with the measured dose. It will also be in this region. be used at the Bulk Shielding Facility (BSF), The reactor is being designed so hat it can be where measwernents will be made of the spectra transported between the TSF artd the BSF with a of neutrons and gamma rays emerging from the minimum amount of dismantling. The fuel can be reactor shield. removed without disturbing the control rods of the Calculations for the SMC have thus far been control chambers. This will be accomplished by directed toward obtaining a go nts in a rotating rig that can be the design effort has been dit a simple yet flexible over-all de on. A removable plug in the rig as it is now planned, is described differences between it and the HE REFLECTOR signs are noted. The SMC s lector of the SMC will be similar CFRMR to show how c the CFRMR, except at the top ere the question of hydraulics e CFRMR design. The sodium May 1' 1957. lector will be simulated Ilium. If cooling is re- Gometry of the CFRMR in the SMC (see Fig. 5.4.1). The first region outside the beryllium reflector The central beryllium island will be cylindrical, will be the first boron curtain. In the CFRMR this and its center will be removed to provide space for region consists of a layer of sodium, followed by 279
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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
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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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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
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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 266 and 267: ANP PROJECT PROGRESS REPORT SECTION
Page 268 and 269: ANP PROJECT PROGRESS REPORT .. .._
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