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42 ORNL-DWG 67- 11789 PORTABLE SHIELD GAMMLI CHAMBER (1%6 in OD) -4 .. 4-in LEAD COLLIMATOR 48 in LONG 1 Fig. - 0 a -, - CENTERLINE COLLIMATOR MOVEMENT ‘ ~ 4 - in COI I IMATOR HOL: , CESIUM J GAMMA SOURCE I 4 2.3. Collimator-Source Geometry for Point-Source Test. DISTANCE 13 Oft (SOURCC OUTOF CARRIER) DISTANCE i5 5fi VEHllCAL (SOURCE OUTOF CARRIER) DISTANCE 15 5ft VERTICAL (SOURCE IN CARRIER) O L 5 4 3 2 1 0 i 2 3 4 5 COLLIMATED SOURCE POSITION TO LEFT OR RIGHT (in Fig. 2.4. Collimated Radiation from 5-curie 137C5 Saurce. --e
significantly, indicating clearly the collimating effect. The flat top at the peak was of the same width as the collimator hole and represents the resolution of the collimator when used with a point source. Gamma Scan of the MSRE Heat Exchanger A gamma radiation scan was made on May 19, 1967, over the area in the reactor cell containing the fuel-to-coolant-salt heat exchanger and fuel salt line 102. To accomplish the radiation scan, the portable maintenance shield was located over an opening in the reactor cell above the heat exchanger, and the collimator and gamma ion chamber were in- stalled in a hole in the portable shield. Measure- ments were made by moving the portable shield until the ion chamber was directly above the de- OR N L- 0 WG 6 7- l I791 PORTAB1.E , [/ ION CIiAMBFii / 48-in. COLLIMAl-OR TUBE ( 4V3. in. OD) -.) ~~ -- INCREASING Y HEAT EXCHANGER 6 ft -3 in. FF 101 FF 102 I 18 it-9 in I 13 ft-2 in. 1 Fig. 2.5. Source-Detector Geometry for Gamma Scan of MSRE Heat Exchanger. 43 sired points in the cell. Figure 2.5 shows the vertical distances from the tip of the ion chamber to items in the cell. The orientation of the various ion chamber traverses of the cell along with lines of equal radiation levels are shown superimposed over the heat exchanger and line 102 in Fig. 2.6. It wilI be noted that the maximum radiation levels were 3.5 r/hr above the heat exchanger center line and 300 mr/hr above line 102. When the collimator was removed, the radiation level at the top of the hole in the portable shield was 100 r/hr. These results show that the collimated gamma ion chamber measures radiation levels with very good resolution of position, even in the presence of high background radiation levels. Therefore, this method of radiation measurement should be useful in locating accumulatiot~s of fission products in reactor components and in planning maintenance operations. Gamma Energy Spectrum Scan of the MSRE Heat Exchanger On May 20, 1967, a gamma energy spectrometer was set up over the same area in the reactor cell, and measurements were made at several points over the fuel-to-coolant-salt heat exchanger. This exploratory experiment was made primarily to evaluate the method. The measurements were made by using a 3- by 3-in, NaI crystal and photomultiplier tube mounted in a lead shield which had a collimating hole '/32 in. in diameter and 7 in. long under the crystal. The array was mounted on the hole in the portable shield in the same manner as the collimator for the gamma scan described earlier. There were strong, well-defined peaks at about 0.48 and 0.78 Mev corresponding to Io3Ru and "Zr-95Nb. The resolution of the NaI crystal was not good enough to determine whether the second peak was from g5Nb only or from the "Zr decay chain. The energy resolution could be improved by using a different crystal, since the collimator did not appear to degrade the peaks. The problem of assigning absolute disintegration rates to these isotopes is complicated by the geometrical arrangement of the heat exchanger and heaters, ihe effect of gamma energy on absorption by the collimator, the source distribution in the heat exchanger, and the counter efficiency. It is believed, however, that some measure of the relative
Page 3 and 4: c c c Contract No. W-.740 5-eng- 26
Page 5 and 6: , INTRODUCTION ....................
Page 7 and 8: 7 . SYSTEMS AND COMPONENTS DEVELOPM
Page 9 and 10: . 15.7 Oxygen Analysis ............
Page 11 and 12: i The objective of the Molten-Salt
Page 13 and 14: PART 1. MOLTEN-SALT REACTOR EXPERIM
Page 15 and 16: PART 2. MSBR DESlGN AND DEVELOPMENT
Page 17 and 18: especially when the system is stabi
Page 19 and 20: generated species in molten fluorid
Page 21 and 22: cold leg. The second loop, of Naste
Page 23 and 24: Part 1. Molten-Salt Reactor Experim
Page 25 and 26: was at full power continuously exce
Page 27 and 28: Analysis and details of operations
Page 29 and 30: 1.2 REACTlVlTY BALANCE J. R. Engel
Page 31 and 32: alance results during this time sho
Page 33 and 34: II_- - 23 Table 1.2. MSRE Cumulotiv
Page 35 and 36: 4 2 5 10 20 transient that followed
Page 37 and 38: 27 Fig. 1.13. Motor of Reactor Cell
Page 39 and 40: personnel access to the area where
Page 41 and 42: accumulation rate at present indica
Page 43 and 44: The retrieval of the sample latch w
Page 45 and 46: The moisture condensed from the cel
Page 47 and 48: MSRE, details of some of the equipm
Page 49 and 50: 39 Fig. 2.2. General View of Latch
Page 51: c 41 Table 2.1. Radiation Levels Fo
Page 55 and 56: 2.5 PUMPS P. G. Smith A. G. Grindel
Page 57 and 58: 3.1 MSRE OPERATING EXPE RI ENCE C.
Page 59 and 60: The rate-of-fill interlocks, includ
Page 61 and 62: 16 15 44 (3 42 I1 9 51 LLETHARGY 8
Page 63 and 64: shown as solid points in Fig. 4.1 (
Page 65 and 66: These are the results of two-dimens
Page 67 and 68: . r. ~ ~ ~ Fig. 4.8. Axiol Distribu
Page 69 and 70: . 59 Fig. 4.10. Axial Distribution
Page 71 and 72: - 12 0.0 $ 04 Lo ... z ? I- ;s -04
Page 73 and 74: Part 2. MSBR Design and Development
Page 75 and 76: ather than just the core and to pro
Page 77 and 78: A . 9.
Page 79 and 80: 0 2 4 6810 LLLLLLU 1 INCHES COOLING
Page 81 and 82: however, electric heaters are provi
Page 84 and 85: I 43ft 3in REACTOR ’ t 40in. ! 3i
Page 86 and 87: of machining or close tolerances. T
Page 88 and 89: GASCONN I GAS SKIRT 4ft 8in. OD 19f
Page 90 and 91: 271 TIRES 2%. A PITCH L- STEAM (la
Page 92 and 93: 6.1 MSBR PHYSICS ANALYSIS 0. L. Smi
Page 94 and 95: 4 V S; 0.06 v F 2.25 2.24 2.23 2.22
Page 96 and 97: 0 8 6 4 7- 4=H20 SPECTRUM 2=D20 SPE
Page 98 and 99: chief indicators of performance. Th
Page 100 and 101: Work related to the Molten-Salt Bre
Page 102 and 103:
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
Page 114 and 115:
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
Page 120 and 121:
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 -~
Page 134 and 135:
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
Page 142 and 143:
SAMPLES in. DlAM X t'46 in. ,,/NOR-
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c( 0 c c 0 134
Page 146 and 147:
10.1 OXIDE CHEMISTRY OF ThF,-UF, ME
Page 148 and 149:
BeF, in 2LiF 13eF,, this partial pr
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(up to one week) the transparency o
Page 152 and 153:
The appearance in appreciable conce
Page 154 and 155:
MoF3 e h l o .... ~~ .... Mo t MoF,
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i observed peak heights for Mo 2F9
Page 158 and 159:
12.1 EXTRACT] ROTACTlNlUM FROM ever
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2 a STATIC -~ -0 AGITATED A AVERAGE
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to the end of the nickel anode. A m
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centration (97% removed). The distr
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point marked with a cross is the va
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13. FB u orate 13.1 PHASE RELATIONS
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THERMOCOUPI-F FURNACE I TO VACUUM O
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Cr Metal Hastelloy N Fe Mo ~ 162 Ta
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- 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
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This uranium species disappeared sl
Page 184 and 185:
174 BI I - CARRIER - ...... -+ SAMP
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olten- I rr Molten-salt breeder rea
Page 188 and 189:
I COLD LEG RETURN LIN 178 CORE OUTL
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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
Page 202 and 203:
P c9 P 082 P 8'ZF P 1.11 .c OF P S0
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
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others, but all three stringers in
Page 212 and 213:
- Y) a - 70 60 50 40 (0 m 30 + m 20
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204 Fig. 16.7. Photomicrographs of
Page 216:
206 Fig. 16.9. Photomicrographs of
Page 219 and 220:
AXF-5QRG 4-4 4 a9g/rm3 4f 56 % ~ AX
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Carbon Corporation, Poco Graphite,
Page 223 and 224:
was found. In view of the low react
Page 225 and 226:
SIC TEMPERATURE STAINLESS STEEL TUB
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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
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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
Page 261 and 262:
25. Modifications to MSRE Fuel Proc
Page 263:
nickel line through a sintered meta
Page 267 and 268:
1. R. K. Adams 2. G. M. Adamson 3.
Page 269 and 270:
344. E. H. Taylor 345. W. Terry 346
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