ORNL-4191 - the Molten Salt Energy Technologies Web Site

More documents

Recommendations

Info

Our materials program has been concerned both with the operation of the MSRE and with the development of materials for an advanced MSBR. 'The primary role of the materials program in the operation of the MSRE has been a surveillance program in which we follow the property changes of the MSRE graphite and Hastelloy N as the reactor operates, We have surveillance facilities in the reactor core and on the outside of the core tank. The successful operation of the MSRE has strengthened our confidence in the molten-salt re- 16. AA 16.1 GENERAL DESCRIPTION OF THE SURVEILLANCE FACILITY AND OBSERVATlONS ON SAMPLES REMOVED W. H. Cook terial t H. E. McCoy J. R. Weir The effects of the operational environments of the MSKE on its unclad moderator of grade CGB graphite and its structural alloy of Hastelloy N continue to be monitored periodically with surveillance specimens of these materials. The surveillance assembly, the general sampling schedule, and the examination program have been described previously. The second group of reactor core specimens, stringer RS2, has been removed from the core after accumulating peak fast- (E > 0.18 MeV) and thermalneutron doses of approximately 1 x loz1 and 4 x lo2 neutrons/cm2 respectively. These specimens were subjected to a temperature of 1190 +_ 18OF for 5500 hr. The first group of vessel specimens, 'MSR Program Semiann. Progr. Rept. Aug. 31, 1965, ORNL-3872, pp. 87-92. 196 actor concept, and we have initiated a materials program in support of an MSBR. In this reactor the graphite will be a primary structural material, since it separates the breeder and the fuel salts. Hastelloy N will be the metallic structural material, and it will be necessary to develop a joint between graphite and Hastelloy N. Thus, most of our re. search effort is concerned with the structural materials, graphite and Hastelloy N, and the joint between thcm. stringer X1, was also removed. The peak thermalneutron dose on these is approximately 2.5 x 10'' neutrons/cm2. 'The estimated temperature range on these specimens was 900 to 1200°F, and the time at temperature was approximately 11,000 hr. Initial results of examination of these groups have not re- vealed any unexpected or serious effects. These two groups have been replaced with new sets of specimens which are being exposed in the MSRE environments together with other groups that were not sampled at this time. To review briefly, the reactor core surveillance specimens consist of both graphite and Hastelloy N mounted approximately 3 in. away from, and parallel with, the axial center line of the moderator core. The reactor vessel specimens are Hastelloy N mounted approximately 4'5 in. outside the reactor vessel. The reactor core specimens are exposed to the molten fluoride fuel, and the reactor vessel specimens are exposed to the nitrogen-2 to 5 vol % oxygen atmosphere of the reactor containment cell. The result is that the current and future irradiation
,? P Table 16.1. Status of and Future Plans for the MSRE Surveillance Program" Total Stringer Pulled Peak Heutron Dose Stringer Inserted Sampiing Approximare Core Vessel Stringer \lessel' Core Vessel Nu Power (Mwhr) Date Des:gnatlonb Gral,h,tec ~~ Has1e:loy ?J Heat No.d Designation Hsstelloy N Heat ?lo. Faste i-hermaI Thermai ~~ .-- Designarion Graphite Hasteiloy Heat No. Desigcation hastelioy Heat No I 7,820 7-28-56 RS1, RRI, CGB mi None None 3.2 x lozo 1.5 x lozo 6.5 x RS2 CGB 215458 Xone None RL1 5085 21554h XL2 CCB 5065 5085 RR2 CGB 5065 5085 2 32,450 5-9-67 3 50,000 January 1968 4 Ti),@OO July 196P 5 90.000 March 1969 RSZ RS3 RX2 RS4 RR3 RL2 HS5 KR4 CGB 21545 21554 CGR 67-502 ASr-jgSG 67-504 CGY 5065 5085 CGB Exptl heat 5 AXF-5QSG Exptl heat 5 CGB Exptl heat 7 Exptl graphite Exptl hea: 3 CGB 5065 5085 CGB Exptl heat 9 Expil graphi:e Exptl heat 10 CGB Expti heat 11 Exprl graphite Expil heat 12 X1 5065 5085 x2, x3 'Planned and compi!ed by a. H. Cook, 13. E. licCoy, A. Taboada, and others. bAll these reactor core specmens have control specinens exposed io a static fuei S ~ under C MSRE conditions rrctp that there is no neutroi: radiation. .Graphite grade designations: Grade CGB 1s the MSRE moderator graphite which IS anisotropic. Grade AXF-5QBG is sn isotropic graphite. Enptl graphi:e iefers to otber experin;entaI grades of isotropic graphite. 'Has:e::oy N hcat no. :efers to the heat number of a standard Hastehy M composition unless noted otherw.se. Enptl heat refers io modifications of the basic Ilasteiloy N :ha! are to bo detuinined later. "Based on a cdculated iiux sup:,lied by J. H. Engei for nrulmns wtth E > 0.13 Llev ):4 9.9 x 1OZo 4.1 x IOzo 2.7 10'9 7.1 x lozo 2.9 x 10" 1.7 x io2' 7.0x iozo 8.1 x 1020 3.3 x 1020 3.1 x IO2' 3.3 x io2' 3.3 1021 1.4 in*' 8.1 x iozo 3.3 x lozo 8.1 x 1020 3 3 x 1020 5065 7.4 x 10'0 5085 57-532 4.8 x 10'0 67.504 RS3 CGB 67-5OZk x4 67-502 AXF-5QBG 67-504' 67-504 2.7 1019 CGB-I,' BJ' 4.i x loi9 RS4 CGB Exptl heat 5 AXF-SQBG Expti heat 6 RRS CGB Exp:i sea: 7 Exptl graphite Expt; !heal 8 5.6 x 1019 7.4 x 10'9 RS5 CGB Exptl hea: 9 Expt: graphite Exptl heat 10 RR4 CGB Exptl heat 11 Erptl grephite Exp!l heat I:! 'Api)rormate values :or both the reactor vesse? wa!! and the reactor vessel specmens. CExperimental heat 1 which contains an addltion of 0.52 wt :; TI. 'Experimcntai heat 2 which contains an addition of 0.42 w: % Zr. 'Impregnated with graphjtlzed pitch. :Grade AXF-5QBG grapiitr Lrazed to $10 xith GO Pd-35 XI-5 Cr (wt %j brazing alloy. kExperinectd hear 3 which contains a3di:lans oiO.5 Ti and 2 IU wt $. 'Exgeiimental heat 4 which contains an addition of 0.5 W: % Hf. "To bP c~nc~irrmt with salt change to one using 233U.
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 and 52:
c 41 Table 2.1. Radiation Levels Fo
Page 53 and 54:
significantly, indicating clearly t
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
Page 104 and 105:
L- a w r 94 ORNL-OWG 67-(1815 io‘
Page 106 and 107:
about 500 mm Hg at the test operati
Page 108 and 109:
1 I 1 I 1 98 MOTOR COUPLING dWER BE
Page 110 and 111:
head and flow characteristics of th
Page 112 and 113:
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
Page 116 and 117:
Sample Nc. F312-10 FPi2-1: FP12-12
Page 118 and 119:
~. 108 Table 8.2. Chemical Analyses
Page 120 and 121:
tenfold or more as a consequence of
Page 122 and 123:
mechanism is available which satisf
Page 124 and 125:
An additional purpose of sampling w
Page 126 and 127:
9. Fission Product Behavior in the
Page 128 and 129:
een stripped is more nearly 50% of
Page 130 and 131:
E > 0 12.0
Page 132 and 133:
(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
Page 136 and 137:
126 Table 9.4, Fission Product Depo
Page 138 and 139:
Table 9.7- Approximate Fission Prod
Page 140 and 141:
(e.g., in metallic colloidal aggreg
Page 142 and 143:
SAMPLES in. DlAM X t'46 in. ,,/NOR-
Page 144 and 145:
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
Page 150 and 151:
(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,
Page 156 and 157: i observed peak heights for Mo 2F9
Page 158 and 159: 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
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 208 and 209: 198 SPLIT STRAP SLEEVE BAND (a) S F
Page 210 and 211: others, but all three stringers in
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
Page 216: 206 Fig. 16.9. Photomicrographs of
Page 219 and 220: AXF-5QRG 4-4 4 a9g/rm3 4f 56 % ~ AX
Page 221 and 222: 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
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
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
show all

ORNL-4191 - the Molten Salt Energy Technologies Web Site

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?