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ORNL-TM-3866.txt
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RNL-TM-3866
ot
YR o ;
w0 / |
CORROSION AND MASS TRANSFER
CHARACTERISTICS OF NaBF,—NaF (22-8 mole %)
IN HASTELLOY N
J. W. Koger
THIS DOCUMENT CONFIRMED AS
UNCLASSIFIED
gl\yISION OF CLASSIFICATION
DATE__'_1e/iclHz
GISTRIBUTION OF THIS BOCUMEKT 15 UNLAETED
RIDGE NATIONAL LABORATORY
IO CARBIE R TS R T
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.
A}
)
‘&)
e}
+y
-
ORNL-TM~-3866
Contract No. W-7405-eng-26
METALS AND CERAMICS DIVISION
CORROSION AND MASS TRANSFER CHARACTERISTICS OF NaBF,—NaF (92-8 mole %)
IN HASTELLOY N
J. W. Koger -
. NOTICE
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, com-
pleteness or usefulness of any information, apparatus,
.| product or process disclosed, or represents that its use
would not infringe privately owned rights.
- -~ OCTOBER 1972
NOTICE This document contains information of s preliminary nature
and was prepared primarlw for internal use at the Oak Ridge National ;
Laboratory. It is subject to revision or correction and therefore does
not represent a final report, A
OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennessee 37830
- operated by =
UNION CARBIDE CORPORATION
for the .
U.S. ATOMIC ENERGY COMMISSION
™
R7CES
BISTRIBUTION OF THIS DOCUMENT IS GNLIVHTED
<
iii
CONTENTS
Page
: Abstfact Gt e e e s e e e e e e s e e e e e e e e e e e e e s 1
Introduction « . ¢ ¢ &+ « ¢ ¢ ¢ ¢ 4 v e v e e e e e e e e e e e 1
Experimental Procedure . « « « « « o o o o o o o o ¢ o o & o o o . 6
Equipment . . « ¢ o ¢ ¢ v v o s 0 e e e e e e e e e e e e e e 6
Salt Preparation . . . « ¢ ¢« ¢ ¢ ¢ o 0 ¢ o o o s s s s s s e s 8
AN2lySEeS8 « 4 ¢ o s o o s s s s s s % s e s e s s e e e s s e e 11
Operation and Resulfs Gt e e e s s s e s e ee e e e e e e 11
Thermal Convection Loops NCL-13, NCL-13A, and NCL-14 . . . . . 11
LoOp NCL=17 & & &« ¢ o o s s o o o o o s o s s o o s o s s o o 20
LOOP NCL=20 &+ v v v v v v o o v o v v o oo e w e e e e 2]
FCL-1 Pump LOOD &+ « « « + o « o o o o o o o o o o o o o o » o+ o 28
RUNS 1 8Nd 2 « o v v o o v e e e e e e e e e e . 32
RUL 3 . v v o o o o o o o o o o o o o o s s e e e 0 e o 37
‘ Installation and Testing of Cold Finger During Run 3 . .. 38
) RUN 4 « 4 o o + o o o o o o o o s o s o s s s o oo o« 40
: PP .
RUD 6 &« v ¢ o o o o o o o o o o s o o o s o o o o o o« b5
RUN 7 « o « o o o o o o o o o o s- o o o s o o s o o+ o o 48
Salt ChemiStTY « « &« o & « o o o o o o o o o o o o o o o o o s s o= 33
Purification . . « v « ¢ ¢ « o ¢ o o o s o o o o o s o o = s s I3
Analytical Chemistry . . . . « « ¢« ¢« ¢ ¢ o ¢ ¢ o o o . . .. 54
Discussibn.. « e ..;‘. T . 7
Theory Q e e e e 0 e C e e e e e e e e ... « « o« o 54
Equations . . . . . . s e e e e e s e e e e e e e e 61
Kinetics . . e v e e e C et e s e s e s e s e e 62
‘Solid-State Diffusion Control . . . . . . . .‘.‘. .« +« + - 066
Solution Controlling . .';'. T Y
Experimental Data . . . . . Gt e e e e s e s s e v s e . . 68
- ; Diffusion Calculations . « « o + o o o « o o v o s oo o oo 10
SUmmAYY « o o« o o ; P e e e e e e e e e n e e e s .. 76
COI‘ICluSiOHS s 8 ® s o & 7 e s e s e s s s s 2 s .o . s 8 e | v e s » 78
g ACkDOW].edgment -® 8 8 & 8 & & ¥ 9 8 B2 8 & " » & 4 T v+ s e e = e 2 79
wi)
1)
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CORROSION AND MASS TRANSFER CHARACTERISTICS OF NaBF,—NaF (92-8 mole %)
IN HASTELLOY N |
J. W. Koger
ABSTRACT
A series of corrosion experiments in thermal convection
and pump loops designed to test the compatibility of fused
NaBF,—8 mole % NaF with Hastelloy N has shown the extreme
effect of impurities on the system mass transfer.” The diffi-
" culty in keeping the melt sufficiently pure was also illus-
trated. Kinetic considerations showed that the mass transfer
process is controlled either by solid-state diffusion or by
the solution rate, depending on the amount of impurities
allowed to enter the salt. The mass transfer behavior is
very similar to that for the Cr-UF,4 corrosion reaction
(material removal in the hot section and deposition in the
cold section), the differences being that alloy constituents
other than chromium participate in the process and that the
reaction rates are different. Because of these differences,
the effective diffusion rate controlling the hot leg attack
is larger than that obtained in typical diffusion experi-
" ments for chromium in Hastelloy N.
Titanium-modified Hastelloy N with less chromium and
iron shows a greater resistance to attack in a fluoroborate
salt with 500 ppm oxide impurity than does standard
Hastelloy N. Its corrosion rate is doubled by increasing
the oxide concentration to 1500 ppm. Average corrosion
rates were low for all systems tested.
-~ : ~ INTRODUCTION.
‘The successful development and operation of the molten salt reactor
‘experiment (MSRE) have led to the present program for_ development of a
molten salt breeder reactor (MSBR) In the MSRE the heat transferred
from the fuel salt to the coolant salt was. rejected to an air-cooled
radiator. In the MSER a secondary‘coolant ‘will be required to remove
heat fromltne fuel in the primary heat exchanger and transport this
- heat to supercritical steam at quite low temperatures.
This secondary coolant should have low viscosity and density and
high heat capacity and thermal conductivity to permit use of écceptable
heat exchangers, coolant pumps, and steam generators. The melting point
must be low enough to meet the heat transfer temperature requirements,
and the vapor pressure must be low at the temperature of‘operation. The
salt must also be easily remelted, with‘no precipitation of high-melting
compounds during cboling. The coolant must be commercially available in
high purity, and the price should not be prohibitive. In nuclear systems
the coolant must be stable under the radiation that it encounters. We
_'also must consider the result of accidental mixing of the coolant fluid
and steam and select a codlant in which the effects of this mixing will
_bé minimiied. Last but not least,-the coolant must be compétible,fiith
the container materials .of the system. _ | _
It now appears that the best choice for the MSBR secondary coolant -
is the eutectic mixture of 8 mole % NaF in NaBF4, with a meltihg point! of
385°C (725°F) as shown in Fig. 1. The salt is quite inexpensive
lc. J. Barton, L. V. Gilpatrick, H. Insley, and T. N. McVay, MSR
Program Semiann. Progr. Rept. Feb. 29, 1968, ORNL-4254, p. 166.
1000
\
900 ~
ORNL-DWG 67-9423A
700 —— N ‘
600 - \
500 _ R
TEMPERATURE (°C)
400 - — —
300
200 —1—L —
NaF 20 40 60 80 Nt'JBF4
' NaBF, (mole %) :
Fig. 1. The System NaF-NaBF,, .
7]
C e
wl
(< $0.50/1b). ‘At elevated temperatures the fluoroborates show an
appreciable equilibrium pressure of gaseous BF3; however, at. the
proposed maximum temperature of the MSBR secondary coolant (621 C) the
2
pressure is only 252 torr. ‘The equilibrium pressure above a melt of
NaBF,—8 mole 7 NaF is given as a function of temperature by-
= 0 _ . ' o o
log Ptorr'-'9°024 5920/T( K) .
Table 1 contains some of the pertinent physical properties for this
mixture at temperatures of interest.,‘Other possibilities'for secondary
coolants, sdEh'as'fluorides,_chlorides and liquid metais,'are discussed
3 l+ 5
elsewhere.® Before our compatibility tests with the‘sodium fluoro-
borate‘mixture, little was known or reported about its corrosive behavior
in the molten state. _
Because of its appreciable vapor.gressure at temperatures of
interest, BF 3 oorrosion is of importance'also. In corrosion experiments6
with gaseous BFj3, it was rapidly attacked by traces of moistnre to give
hydroxyfluoboricsacid (HBF 30H) and HF. Also BF3; and glass reacted at
an' appreciable rate just above 200°C. 'Underrthe conditions of those
experiments, BF3; did not appreciably attack a wide variety of metals or
alloys examined at temperatures up to 200°C.
2S Cantor, J. W. Cooke, A S. Dworkin, G D. Robblns, R. E. Thoma,
and G. M. Watson, Physical Properttes of'MbZten Salt Reactor Fuel,
0RNL-TM—2316 (August 1968). ol : , ;
W. R. Grimes, "Molten-Salt Reactor Chemistry," Nch Appl Pechnol.
8: 142 (1970) .
“J. W. Koger and A. P. Litman, Compattbtlzty of Hastelloy N and
Croloy 9M with NaBFy-NaF-KBF, (90-4-6 mole %) Fluoroborate S&Zt
ORNL-TH-2490 (April 1969).
‘53, W. Koger and A. P. Litman, Compatzbzltty of Fused Sodtum
Fluoroborates and BF3 Gas with HasteZZoy N Alloys, ORNL-TM-2978 -
"~ (June 1970).
®F. Hudswell, J. S. Nairn, and K. L. Wilkinson, "Corrosion Experi-
ments with Gaseous Boron Trifluoride,” J. Appl. Chem. 1: 33336 (1951).
Table 1. Some Pfoperties,of theAMixtfire NaBF,—8 moie % NaF
Approximate_meiting_point, °C
. Vapor pressure at 621°C, torr
Density,a g/cm3:
at t°C
‘at 621°C
at 538°C
at 455°C
Viscosifiy,b centipoise;
at T°K
at 621°C
at 538°C
at 455°C
Heat Capacj.ty:c
., = 0.360 cal g~! °c"!
‘Thermal Conductivity:d
e
O & bl
384 -
252
p = 2.252 — 7.11 x 1071
1.82
1.87
1.93
0.0877 exp(2240/T)
at 621°C:K = 0.0039 W cm~! °c~!
at 538°C:K = 0.0041 W cm™}! °c~!?
at 455°C:K = 0.0043 W em™} °C™!
Latent Heat of Fusion = 31 cal/g
#s. Cantor, MSR Program Semtann. Progr. Rept. Aug. 31, 1969,
ORNL-4449, p. 14.
bS. Cantor, MSR Program Semiann. Progr Rept. Aug 31,
A. S. Dworkin, MSR Program Semiann. Progr. Rept. Feb 29 1968,
ORNL-4254, p. 168.
d
ORNL-4449, . 92.
J. W. Cooke, MSR Program Semiann. Progr. Rept. Aug 31, 1969,
1969,
1)
€
‘-“‘)
a)
u)
w)
All metal components of the MSRE in contact with molten salt were
made of Hastelloy’ N (formerly called INOR-8). Two decades of corrosion.
testingt’_15 and e)cperiencew""19 with-the MSRE have demonstrated the
excellent compatibility of‘Hastelloy N and graphite with fluoride salts
containing LiF, BeF,, UF,, and Tth. Hastelloy N, perhaps with some
modification of composition, is quite likely to be the primary contain-
ment material for MSBR. Thus, it was of great interest to the molten
salt program to determine ‘the compatibility of the fluoroborate salt
mixture with Hastelloy N and related alloys. Of Special interest is
Vtemperature-gradient mass transfer, which must always be considered
" where corrosion in a heat exchanger is possible.l Corrosion and deposi—
tion processes ‘in flowing nonisothermal systems are interdependent and
:each exerts considerable influence over the extent ‘and characteristics
of the other. Therefore,'a performance analysis of a nonisothermal
system must consider these processes as complementary and equal in sig—
nificance to the overall system behavior. This paper is an up-to-date,
open-ended report on these studies.
Hastelloy N is the trade name of Cabot Corporation for a nickel—
base alloy containing 16% Mo, 7% Cr, 5% Fe, and 0.057% C
L. S. Richardson, D. C. Vreeland, and W. D. Manly, Cbrrosron by
Molten Fluorides: Interim Report for prtember 1962, ORNL -1491
(April 20 1953) ,
G. M Adamson, R. S. Crouse, and W D ‘Manly, Interzm Report on
Corrosion by Alkali-Metal Fluorides: Wbrk_to Muy 1, _1953 0RNL-2337
(March 20 1959). . _
G. M. Adamson, R. S. Crouse, and W. -D. Manly, Interzm Report on
Corroszon by Ztrcontum-Base Fluorzdes 0RNL-2338 (Jan. 3, 1961)
. 'y, B. Cottrell, T. E. Crabtree, A. L. David, and W. G. Piper, -
Disassembly and Postoperative Examination of the Atrcraft Reactor
Emperzment 0RNL—1868 (April 2, 1958) . _
124, . Manly, G. M Adamson, Jr., J. H. Coobs, J. H. DeVan,
D. A. Douglas, E. E. Hoffman, and P. Patriarca, Aireraft Reactor
EwpertmenteMEtaZZurgtcaZ Aspects, ORNL-2349, pp. 2-24 (Dec. .20, 1957).
134. b. Manly, J. H. Coobs, J H. DeVan, D. A. Douglas, H. Inouye,
P. Patriarca, T. K. Roche, and J. L. Scott, '"Metallurgical Problems in
Molten Fluoride Systems, Progr. Nucl Energy Ser., IV 2: 164-79 (1960).
EXPERIMENTAL PROCEDURE
Equipment
In corrosion‘studies the thermal convection loop represents an
intermediate stage of sophistication and complexity between simple
capsule tests and a fulléscale engineering pump loop experiment. It
is particularly suited to small-scale tests that involve temperature_
gradient mass transfer. The flow of the liquid is caused by its varia-
tion in density with temperature. The development of a modified thermal
convection loop has permitted important strides in ohtaining basic'cOrro—
sion information; The thermal convection loop used in this work and
shown in Fig. 2 permits unrestricted access to specimens and salt at
any time without significantly disturbing 1oop operation or introducing'
air contamination. Access is provided by'twin ball valve arrangements
atop both the hot and cold legs of the loops. The molten salt sampling
r'device illustrated in Fig. 3 was used in our thermal loops and can also
W. D. Manly, J. W. Allen, W. H. Cook, J. H. DeVan, D. A. Douglas,
H. Inouye, D. H. Jansen, P. Patriarca, T. K. Roche, G. M. Slaughter,
A. Taboada, and G. M. Tolson, Fluid Fuel Reactors, pp. 595604,
James A. Lane, H. G. MacPherson and F. Maslan, eds., Addison Wesley,
Reading, Pa., 1958,
J. H. DeVan and R. B. Evans III, "Radiotracer Techniques in the
Study of Corrosion by Molten Fluorides,' pp. 557—79 in Conférence on
Corrosion of Reactor Materials, June 4-8, 1962, Proceedings Vol. II,
Internat10na1 Atomic Energy Agency, Vienna, 1962,
®H. E. McCoy, 4n Evaluation of the Molten-Salt Reactor Emperzment
HusteZZoy N Surveillance Specimens — First Group, ORNL-TM-1997 |
' (November 1967).
"H. E. McCoy, An Evaluation of the Molten-Salt Reactor Emperzment
Hastelloy N Surveillance Specimens —-Second Group, ORNL-TM-2359
(February 1969).
1%y, E. McCoy, An Evaluatton of the MbZten-SaZt Reactor Empertment
Hastelloy N Surveillance Specimens — Third Group, 0RNL-TM—2647
(January 1970) §
H. E. McCoy, An Evaluation of the Molten-Salt Reactor Empérzment'
Hastelloy N Surveillance Speczmens — Fourth Group, ORNL~TM-3063
(March 1971).
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ORNL-DWG 68-3987
STANDPIPE
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s
BALL VALVES
!g! _ TWIN
I
-
©
3
/
| |
1N
' P coamsmere
| |~ HEATERS 1
‘ 30in. '
INSULATION
CORROSION
SPECIMENS-
———
SAMPLER
, . FREEZE :
N VALVES
" OFLUSH o
TANK - , DUMP
AN ' TANK
" Fig. 2. MSRP Natural Circulation Loop and Salt Sampler.
ORNL-DWG 68-2796
. SWAGE LOCK
FITTING
BUCKET -
v
CONNECTION
SAMPLE ' '
REMOVAL SECTION : O
VACUUM "
CONNECTION -
PERMANENT 7
LOOP ASSEMBLY~
BALL VALVE
LFB PUMP
MAXIMUM LIQUID LEVEL
MINIMUM LIQUID LEVEL
Fig. 3. Molten Salt Sampling Device.
be used in pumped 1oofis. Typical thermal convection loops in operation
are shown in Fig. 4.
A forced convection loop was also used to evaluate the fluoroborate
salt mixture and will be described later.
Salt Preparation
The salt for these tests was processed by the Fluoride Processing
Group of the Reactor Chemistry Division. Very pure (> 99.9%7) starting
materials were evacuated to about 380 torr, heated to 150°C in a vessel
-lined with nickel, and then held for about 15 hr under these qonditions.
PHOTO 75125A
¢
FLUSH TANK
A
Fig.
Thermal Convection"Ldops in Operation.
10
If the rise in pressure was not excessive (indicating no volatile impur-
ities), the salt was heated to 500°C while still'Under vacuum and agitated
- for a few hours with bubbling helium. It was then transferred_to the £fill
vessel and from it forced into the loops with‘helium pressure. In the
.case of the pumped loop the salt was transferred initially into a dump
tank and then into the loop tubing.-
The hot portion of each thermal convection loop was heated by sets
of clamshell heaters, with the input power controlled by silicon controlled
rectifiers (SCR units) and-the'temperature‘controlled by a Leeds and
Northrup Speedomax H series 60 type CAT controller.. The loop tempera-
'tures were measured by Chromel-P vs Alumel thermocouples spot welded to
the out31de of the tubing, covered first by quartz tape and then by stain—
less steel shim stock.
‘Each loop was degreased with ethyl alcohol heated to 150°C under
- vacuum to remove moisture, and leak checked before filllng with salt.
All lines from the fill tamk to the loop that were exposed to the fluo-
roborate salt were of the same material as the loop and were cleaned and
tested in the same manner as the loop. All temporary line connections
were made with stainless steel compression fittings. ‘
- Each loop was filled by heating it, the salt pot, and all connecting
lines to at least 530°C and applying helium pressure to the salt pot to
force the salt into the loop. Air was continuously blown on the freeze
valves leading to the dump and flush tanks to provide a positive salt
seal. Tubular electric heaters controlled by variable autotransformers
_heated the cold—leg portions. Once the loop was filled the heaters were
turned off, “and the proper temperature difference was obtained by remov1ng
some insulation to. :expose portions of the cold leg to ambient air.
The -first charge of salt was circulated under a small temperature
difference (20°C) for>24_hr and dumped. This flush removed surface
oxides and-other possible impurities. The loops were then refilled with
new salt and put into operation. A helium cover gas_under_slight posi-
tive pressure (about 5 psig) was maintained over the salt in the loops
~ during operation.
.
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ffand results ‘of all the tests are reviewed.
11
~ Analyses
o Severallmethodsican.be used;to;obtain;quantitative data froma
temperature-gradient mass transfer’experiment relating to the kinetics
of mass transfer, the . thermodynamics.of the process, or both. The most
obvious and easiest to obtain are weight change measurements on specimens
and liquid analyses. The weight changes allow the calculation of mass
transfer rates in both legs, We may also analyze specimens and loop
tubing with a microprobe to determine composition gradients, x-ray
fluorescence to determine the surface composition, and spectrochemistry
to determine overall composition. Standard metallographic examination
is also helpful to determine the extent of attack or void formation in
the hot leg or the amount of deposit in the cold leg.
" OPERATION AND RESULTS
. The results of tests of the fluoroborate salt mixture in two ther-
mal convection loops and in a ‘series of capsule tests have already been"
reported.?%s2} In addition, four other thermal convection‘loops and one
pumped“loop‘have'been'operated. Thése latter tests are described below,
-4
Thermal Convection Loops NCL-13, NCL—13A and NCL-14
Thermal convection loops NCL—13 rand NCL—14 (constructed of standard
Hastelloy,N)_were started at the same time under the identical conditions
of 605°C maximum_temperature and a}temperature~difference of 145°C. .. .
| Theseioperatingrconditions,were,thosefipropoSed for the coolant circuit
~of the_MSRE.A,puring circulation each loop (0.75-in.-OD X 0.072-in.-wall
tubing) contained about 2.7 kg of salt that contacted 1740 cm’® (270, in.?)
2°J W, Koger and A. P. Litman, Compatzbzlzty of Hastelloy N and
iCroZoy M with NaBFu-NuF-KBFg (90-4 6 moZe %) Fluoroborate saZt
ORNL-TM-2490 (April 1969).
213, W. Koger'and A. P.: Litman, Compatzbtltty of‘Fused Sodium
Fluoroborates and BF3 Gas. with Hastelloy N Alloys, ORNL-TM-2978
(June 1970) ‘
12
of surface and traveled 254 cm around the harp. Typical flow under the
above conditions was 7 ft/min. Loop NCL-13 contained standard Hastelloy N
- specimens, while loop NCL-14 had titanium-modified Hastelloy N suspended
in the salt stream. The compositions of these alloys are given in
- Table 2. The modified alloy is being‘considered because of its superior
‘mechanical properties.under radiation’'at elevated temperature.
‘Table 2. Composition of Hastelloy N Alloys
Content, wt %
Allo , ‘ T
y Ni Mo Cr Fe Si Mn Ti
Standard Hastelloy N L 70 17.2 7.4 4,5 .0,6 0.54' 0.02
Titanium-modified Hastelloy N 78 13.6 7.3 < 0.1 < 0.01 0.14 0.5
The weight changes measured for the,specimens‘in NCL-13 and NCL—14
showed an increase in mass transfer rate between 3500 and 4300 hr of '
egpcsute to the salt (Fig. 5). This was accompanied by perturbations in
salt composition. Analyses of the circulating salts from these loops
showed that the oxide content increased to above 2000 ppm (from initially
less than 1000 ppm), and the nickel and molybdenum contents exceeded
100 ppm (from below 25 ppm). Also, the chromium and iron contents
increased "nbrmally"-with time, as shown in Fig. 6.
After 4700 hr of operation, the helium gas regulator that provided -
the ovérpressurerto NCL-13 failed and caused a surge of gas to the loop,
stopping the salt flow. Circulation of the salt could'notfbe resumed
until a vacuum was pulled on the loop, which we believe removed a gas
pocket. Shortly after circulation was restored, an electrical short,
which eventually burned out a heater, occurred and heated the bottom of
the hot 1eg to 870°C (1606°F). This disrupted the flow and caused a
loss of BF3; from the loop, which changed the salt COmposition and plugged
all.thelgas 1ines. The loop was drained of alllsqlt,'and plugged lines
were replaced or unplugged. Other necessary repairs to the loop were
made, and the loop was filled with new salt. The loop was then designafed
as NCL-13A. | I
P
~ ORNL-DWG 68-12031A