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others, but all three stringers in the reactor are bound together. The new stringers for the reactor core specimens and their controls are all pinned at the joints with 0.040-in.-diam Hastelloy N in order to eliminate the pin deformation problem. Studies of the deposition of fission products on the graphite and the Hastelloy N are being conducted by the Reactor Chemistry Division. For their work, they used the graphite specimens from the bottom, middle, and top of the reactor core specimen stringer, plus matching controls and selected Hastelloy N samples from the stringer and basket. The results of their examinations are reported in Chap. 9. The remaining graphite samples are being measured for dimensional changes. Tests of the types outlined in ref. 3 will be made when the dimensional measurements are completed. The results of the examination of the Hastelloy N tensile specimens from the core position and from outside the reactor vessel are reported in detail in Sect. 16.2. We have begun to expose samples in the MSRE core that are of interest for future molten-salt reactors and thus have extended the scope of these studies beyond surveillance of the MSRE. In the specimens just removed, the tensile specimen rods were made of heats of Hastelloy N modified to yield increased resistance to radiation damage. One of the rods had an addition of 0.52 wt % Ti, and the other had 0.42 wt % Zr. Besides evaluating the radiation resistance of these modified alloys, we should also be able to obtain data on their corrosion resistance in the MSRE environment. The alloy modification study was continued in the new stringer, RS3, just returned to the MSRE. One of the tensile specimen rods had an addition of 0.5 wt % Ti and 2 wt % W; the other had an addition of 0.5 wt % Hf. The graphite samples included the anisotropic MSRE graphite (grade CGB), graphitized-pitch impregnated grade CGB graphite, isotropic graphite, pyrolytic graphite, and a joint of isotropic graphite brazed to molybdenum with a 60 Pd-35 Ni-5 Cr (wt %) alloy. Th.is test of the brazed joint with radiation and in flowing salt should supplement the data on corrosion of such joints in static salt without radiation that are discussed later in this section. Since the radiation dose received in the 3MSR Program Semiann. Progr. Rept. Aug. 31, 1965, ORNL-3872, p. 89. 200 MSRE is small compared with what will be en- countered in an MSBR, the primary purpose for in- cluding various grades of graphite is to extend the study of fission product behavior with these grades. The principal objective of this program is to en- sure the safe operation of the MSRE. We are, therefore, continuing to retain 65% or more of the space in the assembly for exposure of the MSRE grades of Hastelloy N and graphite (see Table 16.1). 16.2 MECHANICAL PROPERTIES OF THE MSRE HASTELLOY N SURVEILLANCE SPECIMENS H. E. McCoy The results of tensile tests run on the first group of specimens removed from the MSRE were reported previously. These specimens were removed after 7823 Mwhr of reactor operation, during which they were held at 1190 k 18'F for 4800 hr and accumu- lated a thermal dose of 1.3 x 10'' neutrons/cm2. The creep-rupture tests on these specimens have now been completed, and the results are summarized in Table 16.2. The times to rupture for the surveillance specimens and the controls are compared in Fig. 16.3. The rupture life is reduced greatly as a result of the neutron exposure. However, Fig. 16.4 shows that the minimum creep rate is not appreciably affected. Although the reduction in the rupture life is large, it is quite comparable with what we have observed for specimens irradiated to comparable doses in the ORR in a helium environment. This point is illustrated in Fig. 16.5. The superior rupture life of heat 5081 is evident. The fracture strain is the parameter of greatest concern, since the rupture life does not appear to be reduced greatly by irradiation at low stress levels. The fracture strains for the various heats of irradiated material are compared in Fig. 16.6. The data indi- cate a minimum ductility for a rupture life of 1 to 10 hr, with ductility increasing with increasing rupture life. A lower ductility of heat 5085 after irradiation in the MSRE is also indicated, although the data scatter will not permit this as an un- equivocal conclusion. The superior ductility of heat 5081 and the least ductility of heat 5085 (heat used for the top and bottom heads of the MSRE) are clearly illustrated. 4W. H. Cook and H. E. McCoy, MSR Program Semiann. Progr. Rept. Feb. 28, 1967, ORNL-4119, pp. 95-103.
201 Table 16.2. Postirradiation Creep-Rupture Properties of MSRE Hastelloy N Surveillance R-230 R-266 R-267 R-250 K-229 R-231 R-226 ... 508.5 47,000 5085 40,000 5085 32,400 5085 27,000 5081 47,000 5081 40,000 5081 32,400 Specimensa Irradiated and Tested at 1202OF ........... ................... __._.I Stress Rupture Life Rupture Strain Minimum Creep Kate 0.8 24.2 148.2 2.5.2 8.7 98.7 474.0 R-233 5081 27,000 2137.1 4.25 0.0003 __ . __ ......... __ ....____ aAnnealed 2 hr at 1652°F prior to irradiation. 70 1 0-' 10' io2 HUPTIJRE TIME (hr) 1.45 1.57 1 .os 1.86 2.26 2.65 3.78 0.81 0.031 0.006 0.004 0.20 0.017 0.0059 ORRIL-DWG 67-793a Fig. 16.3. Comparative Creep-Rupture Properties of MSRE Hastefloy N Surveillance and Control Specimens Irradiated and Tested at 120OOF. We also did some further work to determine the whereas the amount of precipitate in he control cause of the reduction in the low-temperature ductility reported previously. Using the extraction replica technique, we found that the irradiated specimens had extensive intergranular precipitation , specimens was much less. Hence, the reduction in low-temperature ductility is probably due to the irradiation-enhanced nucleation on the growth of grain-bourldary precipitates.
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c c c Contract No. W-.740 5-eng- 26
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, INTRODUCTION ....................
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7 . SYSTEMS AND COMPONENTS DEVELOPM
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. 15.7 Oxygen Analysis ............
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i The objective of the Molten-Salt
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PART 1. MOLTEN-SALT REACTOR EXPERIM
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PART 2. MSBR DESlGN AND DEVELOPMENT
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especially when the system is stabi
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generated species in molten fluorid
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cold leg. The second loop, of Naste
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Part 1. Molten-Salt Reactor Experim
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was at full power continuously exce
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Analysis and details of operations
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1.2 REACTlVlTY BALANCE J. R. Engel
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alance results during this time sho
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II_- - 23 Table 1.2. MSRE Cumulotiv
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4 2 5 10 20 transient that followed
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27 Fig. 1.13. Motor of Reactor Cell
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personnel access to the area where
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accumulation rate at present indica
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The retrieval of the sample latch w
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The moisture condensed from the cel
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MSRE, details of some of the equipm
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39 Fig. 2.2. General View of Latch
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c 41 Table 2.1. Radiation Levels Fo
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significantly, indicating clearly t
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2.5 PUMPS P. G. Smith A. G. Grindel
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3.1 MSRE OPERATING EXPE RI ENCE C.
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The rate-of-fill interlocks, includ
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16 15 44 (3 42 I1 9 51 LLETHARGY 8
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shown as solid points in Fig. 4.1 (
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These are the results of two-dimens
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. r. ~ ~ ~ Fig. 4.8. Axiol Distribu
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. 59 Fig. 4.10. Axial Distribution
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- 12 0.0 $ 04 Lo ... z ? I- ;s -04
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Part 2. MSBR Design and Development
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ather than just the core and to pro
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A . 9.
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0 2 4 6810 LLLLLLU 1 INCHES COOLING
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however, electric heaters are provi
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I 43ft 3in REACTOR ’ t 40in. ! 3i
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of machining or close tolerances. T
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GASCONN I GAS SKIRT 4ft 8in. OD 19f
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271 TIRES 2%. A PITCH L- STEAM (la
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6.1 MSBR PHYSICS ANALYSIS 0. L. Smi
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4 V S; 0.06 v F 2.25 2.24 2.23 2.22
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0 8 6 4 7- 4=H20 SPECTRUM 2=D20 SPE
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chief indicators of performance. Th
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Work related to the Molten-Salt Bre
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I- 92 -Clt NO ClRCUl ATING BUBBLES
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L- a w r 94 ORNL-OWG 67-(1815 io‘
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about 500 mm Hg at the test operati
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1 I 1 I 1 98 MOTOR COUPLING dWER BE
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head and flow characteristics of th
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The chemical research and developme
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0 'i! m 0 w m d m w 0 W m 9 4 w lx
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Sample Nc. F312-10 FPi2-1: FP12-12
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~. 108 Table 8.2. Chemical Analyses
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tenfold or more as a consequence of
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mechanism is available which satisf
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An additional purpose of sampling w
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9. Fission Product Behavior in the
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een stripped is more nearly 50% of
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E > 0 12.0
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(014 5 2 4 o~~ 40" 5 2 5 - BLANK -~
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loi3 5 2 40’2 E : 5 m L al a 0) i
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126 Table 9.4, Fission Product Depo
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Table 9.7- Approximate Fission Prod
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(e.g., in metallic colloidal aggreg
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SAMPLES in. DlAM X t'46 in. ,,/NOR-
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c( 0 c c 0 134
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10.1 OXIDE CHEMISTRY OF ThF,-UF, ME
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BeF, in 2LiF 13eF,, this partial pr
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(up to one week) the transparency o
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The appearance in appreciable conce
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MoF3 e h l o .... ~~ .... Mo t MoF,
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i observed peak heights for Mo 2F9
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12.1 EXTRACT] ROTACTlNlUM FROM ever
Page 160 and 161: 2 a STATIC -~ -0 AGITATED A AVERAGE
Page 162 and 163: to the end of the nickel anode. A m
Page 164 and 165: centration (97% removed). The distr
Page 166 and 167: point marked with a cross is the va
Page 168 and 169: 13. FB u orate 13.1 PHASE RELATIONS
Page 170 and 171: THERMOCOUPI-F FURNACE I TO VACUUM O
Page 172 and 173: Cr Metal Hastelloy N Fe Mo ~ 162 Ta
Page 174 and 175: - 0 0.44 0.40 0.36 0.32 .- + z 0.28
Page 176 and 177: . Development and E aluation of for
Page 178 and 179: Sample No. M Wil 1 FP-9-4 FP-10-25
Page 180 and 181: LJ !+€AD POT I I I I I I I I 1 I
Page 182 and 183: This uranium species disappeared sl
Page 184 and 185: 174 BI I - CARRIER - ...... -+ SAMP
Page 186 and 187: olten- I rr Molten-salt breeder rea
Page 188 and 189: I COLD LEG RETURN LIN 178 CORE OUTL
Page 190 and 191: March 17 following the fission prod
Page 192 and 193: Table 15.3. Comparison of Values fo
Page 194 and 195: likely cause of failure is the rapi
Page 196 and 197: 186 Fig. 15.6. Inner Surfoce of Col
Page 198 and 199: 188 Fig. 15.8. Inner Surface of Cor
Page 200 and 201: on final salt samples. 'This value
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Page 204 and 205: HFIR FUEL ELLEMENT ,EXPERIMEUT 194
Page 206 and 207: Our materials program has been conc
Page 208 and 209: 198 SPLIT STRAP SLEEVE BAND (a) S F
Page 212 and 213: - Y) a - 70 60 50 40 (0 m 30 + m 20
Page 214 and 215: 204 Fig. 16.7. Photomicrographs of
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Page 223 and 224: was found. In view of the low react
Page 225 and 226: SIC TEMPERATURE STAINLESS STEEL TUB
Page 227 and 228: 18.1. IMPRQVING THE RESISTANCE are
Page 229 and 230: These aging studies will be expande
Page 231 and 232: 221 Fig. 18.3. Hastellay N Containi
Page 233 and 234: Fig. 18.5. Hasvellcy N (Titanium Mo
Page 235 and 236: ORWL-DWG 67-tIP39 !-in -THICK PLATE
Page 237 and 238: 227 Toble 18.3. Thermal Convection
Page 239 and 240: 229 ORNL-DWG 67-io980 Impurity Anal
Page 241 and 242: 231 Fig. 18.16. Hastelloy N Thermal
Page 243 and 244: time what the effective diffusiviti
Page 245 and 246: Figure 18.20 shows an area near the
Page 247 and 248: The third design, which is also a d
Page 249 and 250: Part 6. Molten-Salt Processing and
Page 251 and 252: that the behavior of the rare-earth
Page 253 and 254: 22. Distillation of MSRE Fuel Carri
Page 255 and 256: 23. Steady-State Fission Product Co
Page 257 and 258: sec (50 hr). These latter residence
Page 259 and 260: analysis of filtered samples and th
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25. Modifications to MSRE Fuel Proc
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nickel line through a sintered meta
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1. R. K. Adams 2. G. M. Adamson 3.
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344. E. H. Taylor 345. W. Terry 346
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