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ORNL-TM-3863.txt
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ORNL-TM-3863
DESIGN AND OPERATION OF A
FORCED-CIRCULATION CORROSION TEST
FACILITY { MSR-FCL-1) EMPLOYING HASTELLOY N
ALLOY AND SODIUM FLUOROBORATE SALT
W. R. Huntley
P. A. Gnadt
MASTER
QISTRIBUTION OF THIS DOCOWENT 1S ORLMIT
This report was prepared as an account of work sponsored by the United
States Government. Neither the United States nor the United States Atomic
Energy Commission, nor any of their employees, nor any of their contractors,
subcontractors, or their employees, makes any warranty, express or implied, or
assumes any legal liability or responsibility for the accuracy, completeness or
usefulness of any information, apparatus, product or process disclosed, or
represents that its use would not infringe privately owned rights.
&
3
«d
)
ORNL-TM- 3863
Contract No. W-Th05-eng-26 -
Reactor Division
DESIGN AND OPERATION ”
| OF A FORCED-CIRCULA
TEST FACILITY (MSR-FCL-1) EMPLOYING Hfzstgglgggxz 128 o
ATIOY AND SODIUM FLUOROBORATE SALT
W. R. Huntley P. A. Gnadt
W
——————me— N O T | CE
This report was prepared as snt account of work |
sponsored by the United States Government, Neither
the United States nor the United States Atomic Energy
Commission, nor any of their employees, nor any of
their contractors, subcontractors, of their employees,
makes any warranty, express or implied, or assumes any
legal lisbility of responsibility for the accuracy, com-
pleteness or usefulness of any information, apparatus,
product or process disclosed, or represents that its use
would not infringe privately owned rights,
JANUARY 1973
OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennessee 37830
operated by
UNION CARBIDE CORPORATION | | |
for the i
U.S. ATOMIC ENERGY COMMISSION
DISTRIEUTION OF THIS DOCUMENT 1S UNLIMITE
”
A
o
iii
CONTENTS
ABSTRACT veveeevvovaceassassssssossasssosasvasssassssnacsassassas
1. INTRODUCTION ...... s sesseassaseasscssarnanse ceeescerssesnas
2. DESIGN AND FABRICATION ..cvvecevascssccssccacccaasnses ceeenas
2.1 Design Criteria .....ccec0vcee resesstesastnsesensnans .
2.2 General Design Information ............ e eeeen
2.3 Detalled Design and Fabrication ..........ccccceeneee
2.3.1 Heater ...ccecevcececscsnccsnccoass Coeteraacae
2.3.2 COO0ler ...iieevscocrorsassonsncsonns trreevnane .
2.3.3 Salt pump «csvevcceness ceseesseavesscasessarsnce
2.3.4 Salt sampler ....... Cereereceneseatacttareaana
2.3.5 BF; system .......000000e ceeenereanaa ceeaese .o
2.3.6 Fill and drain ta8nK ...cevererertvccnnnccannes
2.3.7 ‘Corrosion specimen design ..... ceseseasssenene
2.3.8 Electrical system ......... ceeeens ceeseeiraans
2.3.9 Instrumentation and control ..........cc00cue
2.4 Quality ASsSUTance .......oeeeeeeees R Ceeeeionenans
3. OPERATING EXPERIENCE s veuvuvencnsensnnensnnrnennenrenenes
3.1 Heat Transfer Performance of Sodium Fluoroborate ....
3.2 BFy Handling ........ ceesecernas ceceessaccsorassereans
3.3 Salt PUmp OPETBtLON we.eeneenenenenennenenencnsenenns
3.4 Corrosion Specimen Removal ......ccveeeveennn. ceeeeas
3.5 Salt Sampling ..veeeeeseccrenseroonaessanasnnonsonnns
3.6 Summary of Corrosion RESULLE ...ceeeessvnsessasosnnns
CONCLUSIONS e v evenennnsnncncnsnsnnenenenennses
RECOMMENDATTONS s ¢« e e eeeseaensocanencnensassosnensesancnsnsns
) APPEND]X A- MSR-FCL-l FIIOWSHEE.P oaco.-co-oooo--oo-coccoooco.ocov
APPENDIX B. MSR-FCL-1 CONTROL SYSTEM DESCRIPTION AND OPERATING
PROCEDURES_FOR‘UNATTENDED OPERATION .ecvececscnes
APPENDIX C. MSR-FCL-1 SALT SAMPLING FROCEDURE .,.}............
r
§
W O O N0 PP - A
FE R R R OEW N D PR
EFREFFFEFERBRIRIRLLELE 5B
O\
w
1)
v
ACKNOWLEDGMENT
The fabrication end operation of the test loop were the joint
responsibility of the ORNL Metals and‘Ceramics Division and the ORNL
Reactor Division. The authors wish to thank the many personnel who
alded in the design, installation, operation, and posteoperational
examination of this test.
Special thanks are extended to the following personnel who were
instrumental in the success of the experifient.
H. E. MCCoy, Metals and Céramics Division, and R. E. MacPherson,
Reactor Division, for thelr guidance of the test program.
J. W. Koger, Metals and Ceramics Division, for metallurgical analy-
sis throughout the program.
H. C. Savage, Reactor Chemistry Division, for guidance of loop
operation during the latter portion of the test period and for the
Control System Description of Appendix B.
E. J. Breeding, R. D. Stulting, and L. C. Fuller, Reactor Division,
for their contribution to the detailed design of the system.
%
"
7h
DESTIGN AND OPERATION OF A FORCED-CIRCULATION CORROSION
TEST FACILITY (MSR-FCL-1) EMPLOYING HASTELLOY N
ALLOY AND SODIUM FLUOROBORATE SALT
W. R. Huntley P. A, Gnadt
- ABSTRACT
A forced-circulstion loop (MSR-FCL-1) was assembled and
operated to evaluate the compatibility of standard Hastelloy N
with sodium fluoroborate—sodium fluoride eutectic (NaBF,-8
mole % NaF) coolant salt at operating conditions expected in
the Molten-Salt Reactor Experiment coolant circuit. The salt
velocity in 1/2-in.-0D, 0.042-in.-wall tubing was nominally
10 fps. Hastelloy N corrosion specimens were exposed to the
circulating salt at temperatures of 950, 1030, and 1090°F.
The test has operated more than 10 000 hr at these conditions
and tests are continuing. This report is mainly concerned
with the design, fabrication, and operation of the facility.
Special problems related to accommodating the BFs vapor pres-
sure of the salt were resolved, and the sodium fluoroborate
demonstrated heat transfer characteristics that could be
approximated by conventional correlations such as the Dittus-
Boelter equation. Corrosion rates generally decreased with
opergting time; for example, the lowest coérrosion rate ob-
served for the 1090°F corrosion specimens during a 2900-hr
test interval was equivalent to 0.0003 in. of uniform materisal
removal per year. :
Kezgprds: molten salt, corrosioh, sodium fluoroborate,
Hastelloy N, design, operation, centrifugsl pump, mass trans-
fer, heat transfer, MSRE, unattended operation.
1. INTRODUCTION
The sodium fluorcborate (NEBF;—S mole % NaF) salt mixture is of
interest as a coolant for the secondary circuit of molten salt reactors
because of its low cost (~$0. 50/Ib) and relatively low melting point
(725 F) Screening tests in thermal-convection loops® indicate no seri-
ous problems due to reactions between the salt and the proposed reactor
containment material, Hastelloy N.
3. W. Koger and A. P. Litman, MSR Program Semiannu. Progr. Rep.
Feb. 28, 1969, ORNL-4396, p. 2L6.
The forced-circulation.loop'described here (MSR-FCL-1) represents a
more sophisticated test of the compatibility of the candidate salt and
Hastelloy N. High coolant velocities were used, and the design thermsl
gradient was applied to the system. The results from this test will
assist in the evaluation of the corrosion resistance of the Hastelloy N
containment material and the mass transfer interactions of the contain-
ment material and salt. Detailed metallurgical results will be presented
separately._ '
2. DESIGN AND FABRICATION
2.1 Design Criteria
The MSR-FCL-1 test was designed to evaluate the use of sodium fluoro-
-boratez salt in contact with Hastelloy N alloy containment material at
conditions simulating the secondary-coolant (high-temperature side of the
~ steam generator) circuit of molten-salt reactors.' One objective of the
test was to develop the technology associated with the new salt by using
it in a relatively complex operating system. -
‘The BFy vapor pressure of the sodium fluordborate salt is higher
(e.g., 1h1 mm Hg at the maximum loop temperature of 1090°F) then the
vapor pressure of other salts developed for use in molten—salt reactors.
Accommodating the BFy vapor pressure of the salt at elevated temperature
in MSR-FCL-~1 was a major design prdblem, since BF; is a noxious gas and'
s design to provide adequate ventilation for personnel protection was
required.
An existing system desigr® was used as a basis for MSR-FCL-1. Cen-
tringal pumps, air blowers, electrical transformers, and miscellaneous
_control equipment used in previous corrosion tests of this type were
®Unless otherwise indicated the term sodium fluorcborate will be
used in this report to designate the NaBF,—8 mole % NaF eutectic mixture.
8J. L. Crowley, W. B. McDonald, and D. L. Clark, Design and Opera-
tion of Forced-Circulation Testing Loops with Molten Salt, ORNL-TM-SQB
(May 1963).
Yy
0
oy
LL]
<)
availsble. The reuse of the availsble instrument and conmtrol design and
the existing equipment resulted in a system of limited flexibility; how-
ever, these design features had been previously tested and funds were
only available for minimum redesign and fabrication of new equipment.
The hydraulic characteristics of the ekisting pump were g specific limit-
ing factor on loop performance. '
The facility was originally designed to operate for 10,000 hr and
to provide a maximm bulk fluid salt temperature of 1125°F, a bulk fluid
AT of 275°F at a velocity of T 1/4 fps (3 gpm), and a total heat input
‘of 94 kW. However, the ioop was not operated st these conditions. After
the originél design was completed and before the loop fabrication was
complete, the test conditions were changed to more nearly match the tem-
perature profile of the coolant circuit of the Molten-Salt Reactor Experi-
ment (MSRE), which was then operating. This modificetion to program plans
was a prelude to the proposed introduction of sodium fluorcborate into the
secondary-coolant circuit of the MSRE; The test facility was operated at
a maximum bulk fluid temperature of 1090°F, a bulk fluid AT of LLO°F at a
velocity of 10 fps (4 gpm), and a total heat input of 53 kW.
Corrosion specimens were introducéd into the system at appropriate
" locations to obtaln accurate weight change, chemistry change, and metal-
lographic data. Periodic removal and reinsertion of the specimens were
specified at approximately 2000-hr intervals. Salt sampling at approxi-
mately 500-hr intervals was specified to permit chemical analyses nec-
essary for chargcterization of corrosion processes occurring during
operation. |
Protective instrumentation end an auxiliary power supply were pro-
vided in an attempt to prevent sccidental freezing of the'salt.due to
lose of normal electricai supply or & pump stoppage. Originally this
proteétive system was to be continuously monitored by facility operators;
however, evening and night shift operator coverage’fias discontinued
during the latter part of the operating period and the facility had to
be modified for unattended operation.
2.2 General Design Information
A simplified schematic drawing of the test loop is shown in Fig. 1,
and an isometric drawing of the equipment is shown in Fig. 2. A complete
flowsheet is included as Appendix A. Sodium fluoroborate is discharged
downward from the salt pump (model LFB) at a_temperatfire of 950°F and at
a flow rate of 4 gpm. The salt enters the first of two heat input sections
and is heated to 1030°F; flows over three Hastelloy N metallurgical speci-
mens; continues through the second heat input section, where the bulk
fluid temperature is increased to 1090°F; and:flows.over three additional
metallurgical specimens before being cooled‘in 8 hesat exchanger to 950°F.
The cooled salt then flows over two more metallurgical specimens before
returning to the inlet of the pump. S | ‘
The sglt inventory is stored in a sump tank located below the primary
piping system. A high-purity helium gas blanket is maintained above the
salt surfaces in this tank and in the pump to minimize salt.contamination.
A dip leg in the sump tank allows the liquid salt to be forced by helium
overpressure into the circulating system. The sump tank is designed to
contain approximately twice the salt volume to be circulasted. A freeze
valve serves to isolate the salt in the circulating system from the sump”’
tank inventory. This valve consists of a cooling air line installed
around the 1/h+in.-0D, 0.035-in.-wall tubing connecting the sump tank to
the circulating system. Piping of the circulating system is principally
1/2-in.-0D by 0.042-in.-wall Hastelloy N tubing.
No direct flow measuring equipment is provided in the circulating-
salt system; provisions are made to measure the flow calorimetrically.
Three calibrated Chromel-Alumel thermocouples are installed at both the
inlet and exit of one of the heater sections. By determining the thermal
losses from this section at several temperature levels with no salt in
the system, it is possible to obtain the net electrical heat input during
operation. Flow rates can then be calculated from the net electrical n
power input and the ohserved temperasture rise in the salt as it passed
through the hesgter. '
Engineering parsmeters of the system are shown in Teble 1, and com-
position and physical properties of sodium fluoroborate'are shown in
Table 2. | |
o
H
ORNL-DWG €8-279TR2
SALT
SAMPLE
LINE AJUSTO SPEDE
5 hp MOTOR
— _ QIL LINES
[[ TO PUMP
GAS
LINES 050 *F
TO _
PUMP / METALLURGICAL
OPERATING "/ SPECIMEN
PRESSURE 7 psig 1030 *F
LFB PUMP RESISTANCE HEATED SECTION
1090 °F
METALLURGICAL
SPECIMEN
FINNED
COOLER
BLOWER
METALLURGICAL
SPECIMEN /HEATER LUG (TYPICAL)
Y
o
/‘-' RESISTANCE HEATED SECTION
950 °F
FREEZE
VALVE
E)—— AIR
VELOCITY 10 fps
FLOW RATE - 4 gpm
! SUMP I
o
Fig. 1. Simplified schematic of molten-salt corrosion test loop.
wd
ORNL-LR-OWG 64T40RA
METALLURGY
SAMPLE
10 kva POWER SUPPLY - {DETAIL A)
{MAIN POWER)
1600-amp BREAKER
DETAIL A
METALLURGY
SAMPLE
LFB PUMP
OUTLET
DETAIL B
| 10kva POWER SUPPLY
lll (COOLER PREHEAT)
7~ DUMP TANK
Fig. 2. Molten-salt corrosion testing loop and power supplies.
»h
43
ay
«)
&)
Table 1. Selected engineering data for MSR-FCL-l
Based on actual operéting conditions
Materials, temperatures, and velocities
Tubing and specimens Standard Hastelloy N
Nominal tubing size 1/2 in. OD, 0.042 in. wall
Total tubing length 57 £t
Bulk fluid tempersture (max) 1090°F
Bulk fluid temperature (min) 950°F
Bulk fluid AT 140°F
Flow rate ' Lk gpm
Iiquid velocity A 10 fps
Cooler heat transfer
Heat load at finned cooler 180,900 Btu/hr (~53 kW)
Iiquid Reynolds number B 45,000
Iiquid film heat transfer coefficient ~2000 Btu hr-t ££22 (°F)-?
Iength of finned 1/2-in.-OD cooler coil . 26 fit
Coolant gir flow 995§cfm
Coolant air AT 185 °F
~ Pumping requirements
System AP at 4 gpm 57.5 psi (65 ft)
Required pump speed 5000 rpm
Salt inventory being circulated
Volume in pump bowl 85 in.®
Volume in tubing 46 in.®
Total volume ‘ ) 131 in.%®
Total weight 8.81 1b
- Miscellaneous
Surface to volume ratio for circulating 7 in.2/in.3
salt ' : :
Volume of dump tank - - . 274 in.8
The possibility of leakage of BF, gas through the rotating mechani-
cal face seal of the pump or from the valvés:and'fittings in the pump
seal oil lines exists. To protect pefSonnel from this noxious gas, &
ventilated cabinet is provided to enclose the LFB pump and the‘gas sys- 1
tem. An induced draft blower exhausts the air from the cabinet through
ducts to the roof of the building.
Table 2. Composition and physical properties
of sodium fluoroborate
Composition (mole %)
NeBF, ; 92
NaF . | 8
Approximate molecular weight 10k
Approximate melting point (°F) 125
8 10,656
Vepor pressure; log,, P (mm Hg) = 9.02h4 — -—ffi
At 1090°F 140
At 950°F . , ’ | 29
Densityt’ (1b/ft3)'= 141.4 — 0.0247t ( °F) | |
At 1090°F o 11h.)
At 1020°F -~ 116.2
At 950°F 117.9
Viscosity P (1b £t hrl) = 0.2121 exp —E%QET
At 1090°F 2.86
At 1020°F 3,23
At 950°F 3.7
Heat capacity © [Btu 1v1(°F)"!] 0.360
Thermal conductivity & [Btu hrlft1(°F)~1]
At 1090°F 0.23
At 1020°F 0.235
At 950°F | - 0.2k
83. Cantor et al., Physical Properties of Molten-Salt
Reactor Fuel, Coolant, and Flush Salt, ORNL-TM-2316, p. 33
(Egust 1960).
: S Cantor, MSR Program Semignnu. Progr. Rep. Aug. 31,
_._2J2 ORNL-4449, pp. 1547,
®A. S. Dworkin s MSR Program Semiannu Progr. Rep Feb. 29,
J . W. Cooke, MSR Program Semiannu. Progr Rep. Aug. 31,
1969, ORNL-LL4Lg, p. 92. |
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In addition, a sheet~metal enclosure 1s provided around the salt
,plplng and hegt exchanger to protect operating personnel from gross
- liquid leakage. The system piplng is considered sufficiently reliable
to preclude the need for special exhaust ventllatlon from this enclosure
for protectlon against BF, leakage.. Favorable ventilation conditions
exist in the test areas, which has a 50 ft-high ceiling and continuous
exhaust ventllation
The test loop is shown in Fig. 3 durlng installation of the heaters
and thermocouples. Figure 4 shows the. completed 1nstallatlon
| 2.3_'DEtailed Design and-Fabrication
'2 3 1 Heater
The heat input into the salt is accompllshed by resistance ‘heating
‘two sections of the system piping, each approximastely 105 In. long.
Voltage is applied between two lugs attached to the ends of each heated
- length of pipe. Control is_common to both of the heat input sections
f2.3.2_'Cooler'
Heat is removed from the system by a heat exchanger composed of an
air-cooled, 26-ft-long, 19-in.-diam coil of 1/2-in.-0D by 0.0k2-in.-wall
tubing to which 1/16-in.-thick circular nickel fins are attached (see
Fig. 3). These fins are brazed to the tubing with Coast Metals 52 fur-
nace braze alloy. The finned coil is 1n31de a, sheet-metal housing which
‘ serves as the coollng alr duct.
The salt side pressure drop, as. llmited by the capacity of the salt
'rpump, prohiblts the use of & longer heat exchanger c01l Variations in
fin dlameter and spacing are. used to provide a hlgher heat flux at the
'dhot end of the,oooler. This.geometry creates a flattened salt wall tem-
perature:profile whichlmakesapOSSible'maximum heat-removal‘without cooling
the wall at,the cold end of‘the unit below the 725°F melting point of the
salt. [This feature was importafit during the design stages, when the
expected drop in the bulk fluid temperature was from 1125 to 850°F. It
10
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f heaters and ther-
tallation o
ins
Test loop assembly during
ig. 3.
-mocouples.
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PHOTO 75688
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Fig. 4. Corrosion test loop installed in test stand.
12
became less important when the proposed operating conditions were changed
to simulate the Molten-Salt Reactor Experiment coolant circuit tempersture
profile (1090-950°F).] |
The cooler is resistance heated during preheating of the loop. This
resistance heat system is alSo used to keep the salt above the melting
point during loss of normal Building power. ,Hastelloy N lugs are installed
at the inlet, midpoint, and exit of the coil for attachment of three
electrical leads. The lugs project through holes in the air duét to give
access to the electrical connections. During a loss of normal power the
voltage is supplied to the central lug of the coil from a diesel-generstor
unit used for emergency electrical supply. o
A hinged door, provided on the air exit side of the cooler housing,
is closed to reduce the heat losses during preheating and is equipped to
close autdmatically during & power outage. The top side of this door
and the four sides of the air plenum are insulated with Johns Manville
Kaowool thermal insulation to further reduce the heat losses. This insu-
lation is also used to plug the holes where the electrical lugs penetrate
the air duct.
Air to the cooler 1s supplied through appropriate‘ducting'by a
model 200-A-1 Americen blower with a 3-hp 1725-rpm motor which provides
& maximum air flow of 3200 efm air through the ductwork; However, in
normal operation the alr flow required is about 1000 c¢fm. A throttling
damper is provided to regulate the flow.
Selected engineering data on the actual performance of the cooler
are shown in Tgble 1, along with other engineering parameters of the
system.
2.3.3 Salt pump
The salt pump, model LFB, used in this corrosion test is shown in
Fig. 5. It is a centrifugal sump pump desighed et ORNL and features a
downward discharge. The pump has an overhung vertical shaft, two greése-
sealed ball besrings, and an oil-lubricated mechanical face seal above
the salt liquid level and just below the lower ball bearing. Shaft and
seal cooling are provided by oil which flows downward through the hollow
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13