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ORNL-TM-0202.txt
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WMASTER
OAK RIDGE NATIONAL LABORATORY
7y
o
operated by
UNION CARBIDE CORPORATION
/™ NUCLEAR DIVISION
- for the
™ U.S. ATOMIC ENERGY COMMISSION
« ORNL- TM- 2021, Vol. 1
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8
a‘* '
: EFFECT OF ALLOYING ADDITIONS ON CORROSION BEHAVIOR OF NICKEL -
MOLYBDENUM ALLOYS |IN FUSED FLUORIDE MIXTURES
Thesis)
Jackson Harvey DeVan
’
A This report is a portion of a thesis submitted to the Graduate Council of the University of Tennessee
in partial fulfillment of the requirements for the degree of Master of Science.
ERTRRUTION OF THIS DOCUMEN 15 UNLIMITED
LEGAL NOTICE
This report was prepored as an account of Government sponsorad work. Neither the United States,
nor the Commission, nor any person acting on behalf of the Commission:
A. Mokes any warranty or representotion, expressed or implied, with respect to the accuracy,
completeness, or usefulness of the information contained in this report, or that the use of
any information, apparatus, method, or process disclosed in this report may not infringe
privatsly owned rights; or
8. Assumes any liabilities with respect to the use of, or for damages resulting from the use of
any information, apparatus, method, or process diiclesed in this report.
As used in the above, '‘person acting on behalf of the Commission’’ includes any employse or
contractor of the Commission, or employse of such contractor, to the extent thot such employee
or contractor of the Commission, or employee of such contractor prepares, disseminates, or
provides access to, any information pursuant to his employment or contract with the Commission,
or his employment with such contractor.
LEGAL NOTICE
This report was prepared as an account of Government aponsored work. Neither the ¥United
States, nor the Commission, nor any person acting on behalf of the Commission:
A. Makes any warranty or rejresentation, expressed or implied, with respect to the accu-
racy, completeness, or usefulness of the information contained in this report, or that the use
of any information, apparatus, method, or process disclosed In this report may not infringe
privately owned rights; or ORNL - TM.._ 2 02 :|_
B. Assumes any liabilities with respect to the use of, or for damages resulting from the
use of any information, apparatus, method, or process disclosed in this report. VOl . I
Ag used in the above, “‘person acting on behalf of the Commission”’ includes any em-
ployee or contractor of the Comrnission, or employee of such contractor, to the extent that
such employee or contractor of the Commission, or employee of such contractor prepares,
disseminates, or provides access to, any information pursuant to his employment or contract
with the Commisgion, or his employment with such contractor.
Contract No. W-7405-eng-26
METALS AND CERAMICS DIVISION
EFFECT OF ALIOYING ADDITIONS ON CORROSION BEHAVIOR OF NICKEL-
MOLYBDENUM ALLOYS IN FUSED FLUORIDE MIXTURES
Jackson Harvey DeVan
MAY 1969
This report is a portion of a thesis submitted to the Graduate Cogncil
of the University of Tennessee in partial fulfillment of the requirements
for the degree of Master of Scilence.
OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennessee
operated by
UNION CARBIDE CORPORATION
for the
U.S. ATOMIC ENERGY COMMISSION
WEIRIFULUON OF THIS DOCUMENE 15 UNHWM
iii
CONTENTS
Abstract . . . v v v v i e e e e e e e
Introduction . « .+« v ¢ ¢« ¢« ¢« + ¢ ¢ o o
Review of Related Work . « o« + o« o s o o
Corrosion by Fluoride Mixtures . . .
Corrosion Reactions . . « « . .
Reduction of UF, by Chromium . .
Corrosion of Nickel-Molybdenum Alloys.
Materials and Procedures . . « o o o o @
Tegt Materials . . . « . « « « . . .
Test Equipment . . . . . . . . . .
Salt Preparation . . . . . . « . . .
Operating Procedures « « « « ¢ « « o
Test Examination . .« ¢« ¢ « o o & &
Results and DisCussion . « v o « s o o &
Chromium « ¢« « &« &+ ¢ o o o o o o o o
Corrosion~Product Concentrations .
Metallographic Results . . . . .
Aluminum . v v ¢ 4 o« ¢ o o o« o o o
Corrosgsion-Product Concentrations .
Metallographic Results . « . . .
Titanium . o + & ¢ ¢ ¢ o o o + o o .
Corrosion-Product Concentrations
Metallographic Results . . . . .
Vanadium . . « ¢ ¢ ¢ v ¢ ¢ v 0 o 4
Corrosion-Product Concentrations
Metallographic Results . . . . .
Iron . o v ¢ ¢ 0 i e v e e e e e e
Corrosion-Product Concentrations
-Metallographic Results . . . . .
J
5
00 e oo DWW W
W W W wWww NN DN NN H P e
DO O OO0 0 W ®eEeuw KX P ;e oW
iv
Page
Nio-biu-zn . . . . . * ® - & . . » e . ” - * - - - L] - . . . » . - 32
Corrosion-Product Concentrations . + v o « o v o o o + o« + o 32
Metallographic Results . v v ¢ o o & o « o o o« o o+ o o« o o o 33
TUNESEEIL o v v v v o o v o o o o o o 4 s o e e e e e e e e e . 34
Corrosion-Product Concentrations . . + « o « o o o o o « o« o« 34
Metallographic Results . . « « « « ¢« v o o« o « o . . . ... 36
Relative Thermodynamic Stabilities of Alloying Constituents . . 36
General Discussion of Alloying Effects . « v v v v ¢ « v & » o . 38
Summary and ConcluSions .+ + « « « o o « & « o o o o o o o 0w oo o 40
ACKNOwledgZmENtS « v 4 s v 0 e e e e e e e e e e e e e e e e e e e . 4R
EFFECT OF ALLOYING ADDITIONS ON CORROSION BEHAVIOR OF NICKEL-
MOLYBDENUM ALLOYS IN FUSED FLUORIDE MIXTURES
ABSTRACT
Fused fluoride mixtures containing UF, have been developed
as fuel solutions for high-temperature nuclear reactors. To
develop container materials for such mixtures, we investigated
the corrosion properties of nickel-molybdenum alloys with vari-
ous solid-solution strengthening additions. These evaluations
utilized thermal convection loops which circulated salt mix-
tures between a hot-zone temperature of 815°C and a cold-zone
temperature of 650°C.
The alloys selected for study contained 17 to 20% Mo and
various percentages of Cr, Al, Ti, V, Fe, Nb, and W. Loops of
individual alloys were exposed to the salt mixture NaF-LiF-KF-UF,
(11.2-45,3-41.0-2.5 mole %) for periods of 500 and 1000 hr.
Measurements of the concentrations of corrosion products in
after-test salt samples indicated the corrosion susceptibility
of alloying additions to increase in this order: Fe, Nb, V,
Cr, W, Ti, and Al. However, metallographic examinations of
loop surfaces showed relatively light attack for all alloys
except those containing combined additions of aluminum and
titanium or aluminum and chromium.
A nickel-base alloy containing 17% Mo, 7% Cr, and 5% Fe,
designated Hastelloy N, was found to afford the best combina-
tion of strength and corrosion resistance among the alloy
compositions tested.
INTRODUCTION
Molten fluorides of uranium, thorium, or plutonium, in combination
with other fluoride compounds, have wide applicability as fuels for the
production of nuclear power.! Because of their high boiling points, these
mixtures can be contained at low pressures even at extremely high
operating temperatures. Their chemical and physical properties impart addi-
tional advantages such as excellent stability under irradiation and large
IR. C. Briant and A. M. Weinberg, "Molten Fluorides as Power Reactor
Fuels," Nucl. Sci. Eng. 2, 797-803 (1957).
solubility ranges for both uranium and thorium. These factors have
prompted design studies of molten fluoride fuel systems in conjunction
with thorium-uranium thermal breeders, uranium-plutonium converters, and
uranium burners.
The development of reactors which incorporate a circulating fluoride
salt is predicated on the availability of a construction material which
will contain the salt over long time periods and also afford useful
structural properties. The container material must also be resistant to
air oxidation, be easily formed and welded into relatively complicated
shapes, and be metallurgically stable over a wide temperature range.
In order to provide a material for initial reactor studies, several
commercially available high-temperature alloy systems were evaluated with
respect to the above requirements. As a result of these studies, Inconel,
a nickel-base alloy containing 15 wt % Cr and 7 wt % Fe, was found to
afford the best combination of desired properties and was utilized for
the construction of the Aircraft Reactor Experiment.2 Extensive corro-
sion tests,3’4 as well as posttest examinations of the ARE,” confirmed
the suitability of Inconel as a container material for relatively short-
term fluoride salt exposures. Corrosion rates encountered with this
alloy at temperatures above 700°C, however, were excessive for long-term
use with most fluoride fuel systems.
Utilizing experience gained in corrosion testing of commercial
alloys, we initiated an alloy development program to provide an advanced
container material for fluoride fuel reactor systems. The reference
alloy system was composed of nickel with a primary strengthening addition
of 15-20% Mo. This composition afforded exceptional resistance to fliuo-
ride attack but lacked sufficient mechanical strength and oxidation
W. D. Manly et al., Aircraft Reactor Experiment — Metallurgical
Aspects, ORNL-2349“(1§575.
°G. M. Adamson, R. S. Crouse, and W. D. Manly, Interim Report on
Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953, ORNL-2337
(1959). .
“G. M. Adamson, R, S. Crouse, and W. D. Manly, Interim Report on -
Corrosion by Zirconium-Base Fluorides, ORNL-2338 (1961).
W. B. Cottrell et al., Disassembly and Postoperative Examination
of the Aircraft Reactor Experiment, ORNL-1868 (1958).
resistance at desired operating temperatures. To augment these latter
properties, additions of various solid-solution alloying agents were
evaluated, among them Cr, Al, Ti, Nb, Fe, V, and W. An optimum alloy
composition was selected on the basis of parallel investigations of the
mechanical and corrosion properties which were imparted by each of these
additions. The composition best suited to reactor use was determined to
be within the range 15-17 wt % Mo, 6-8 wt % Cr, 4—6 wt % Fe,
0.04-0.08 wt % C, balance Ni. Subsequent studies of the alloy, desig-
nated Hastelloy N, have shown it to be extremely well suited for appli-
cations demanding long-term compatibility with fluoride salts in the
temperature range 650-800°C.
The present research was concerned with the corrosion effects
resulting from additions of alloying elements to the nickel-molybdenum
system and an analysis of the thermodynamics of the corrosion process as
indicated by these alloying effects.
REVIEW OF RELATED WORK
Corrosion by Fluoride Mixtures
Corrosion Reactions
The corrosion of nickel-base alloys, containing iron and chromium,
by fluoride fuel mixtures has been found to result from a combination
of the following types of oxidation reactionss ©
7
1. Reactions’ involving impurities in the salt
2HF+QI_=CI‘F2 + Hp , (l)
NiF, + Cr = CrFp + Ni , (2)
FeF, + Cr = CrFp + Fe . (3)
*W. D. Manly et al., "Metallurgical Problems in Molten Fluoride
Systems," Progr. Nucl. Energy, Ser. IV 2, 164 (1960).
7"Solid-solution alloying elements are underlined.
2. Reactions involving impurities in or on the metal, for example
2Ni0 + ZrF, = ZrO, + 2NiFs (4)
followed by reaction (2).
3. Reactions involving components in the salt
2UF, + Cr = CrF, + 2UF; , (5)
1l
i
3UF, + Cr = CrF3 + 3UF; . (6)
The extent of the first four of these reactions, which proceed strongly
to the right and to completion rapidly, can be reduced by maintaining low
impurity concentrations iIn the salt and on the surface of the metal.
Reactions (5) and (6), on the other hand, are indigenous to fluoride
systems which derive their usefulness through the containment of UF,.
While the role of chromium has been investigated extensively in connec-
8 considerably less information is available
tion with these reactions,
regarding the thermodynamics of these reactions for the other alloying
elements which were of interest in the present study.
Reduction of UF, by Chromium
The reaction of UF,; with chromium is found to be strongly influenced
by the reaction medium employed.8 In melts composed principally of
NaF-Zr¥F, or NaF-BeFp, the reaction produces only divalent chromium, that is,
2UF, + Cr = 2UF3 + CrTy . (7)
However, in the case of NaF-KF-LiF-UF, mixtures used for this investiga-
tion, the reaction between chromium and UF, produces both divalent and
87. D. Redman, ANP Quart. Progr. Rept. Dec. 31, 1957, ORKL~2440,
pp. 78-82.
trivalent chromium. At equilibrium, approximately 80% of the total
chromium ions in the mixtures are observed to be trivalent, giving the
net reaction
2.8UF, + Cr = 0.2CrFp + 0.8CrF3 + 2.8UF3 . (8)
The equilibrium constant for this reaction is given by
(a )O.Z(Q )O.B(G )2.8
K = CrFs CrF, UF4 . (9)
CHPLICN
where & represents thermodynamic activity. Because of the relatively
small concentrations of CrF, and UFs which are attained in the salt solu-
tions at equilibrium, the activities of each of these components can be
closely approximated by their mole fractions, in accordance with Henry's
law. Thus, for a salt system of fixed UF, concentration, assuming the
reference states for salt components to be the infinitely dilute solution,
(NCng)O.Z(NCrF3)O.8(NUF3)2.8
K = . (10)
(g, )25 (o)
For a system initially containing no UFi, CrF,, or CrF;, it follows that
NCrF2 = 1/4NCrF3 = 1/14NUF3. In such systems where the change in UF,
concentration is small, Eq. (9) reduces to
_ 5/19
Ny, * Norp,) % (11)
where
4/19
o 14/19
iy - 5@;{) (TU% /
O~
The constant KN has been experimentally determined for the mixture
LiF-KF-NaF-UF; (11.2—41.0-45.3-2.5 mole %) by equilibrating it with pure
chromium (agr = 1) at 600 and 800°C (ref. 8). Under these conditions,
the constant is equivalent in value to the mole fraction of chromium ions
in the salt at equilibrium. The measured values of KN are listed in
Table 1.
Table 1. Eguilibrium Concentrationsa of Chromium Fluorides
for the Reaction of Pure Chromium with UF,
Concentration of Chromium
Equilibration Tons in NaF-LiF-KF-UF,
Temperature (11.2-41.0-45.3-2.5 mole %)
(°C)
ppm mole fraction (KN)
600 1100 1.0 x 10~°
800 2600 2.4 % 1072
8J. D. Redman, ANP Quart. Progr. Rept. Dec. 31, 1957,
ORNL-244C, pp. 7882,
Because the chromium-UF, reaction is temperature dependent, chemi-
cal equilibrium beiween these two components is precluded in systems of
uniform alloy composition where the circulating salt continually experi-
ences a temperature change. In such systems chromium tends to be con-
tinually removed from hotter portions and deposited in cooler portions.
A theory relating the rate of this movement to the operating parameters
of the container system has been formulated by Evans.’
Corrosion of Nickel-Molybdenum Alloys
Because of the oxidation of chromium by fuel-bearing fluoride salts,
alloys employing large percentages of this element were not satisfactory
’R. B. Evans, ANP Quart. Progr. Rept. Dec. 31, 1957, ORNL-2440,
pp. 104—113.
as container materials except at temperatures where diffusion rates in
the alloys were relatively low. Accordingly, evaluations were made of
several commercial alloys in which chromium was not employed as a major
alloying addition. Based on these tests, alloys of nickel and molybdenum
appeared to offer the most promising container system for achieving rela-
tively high reactor operating temperatures. Unfortunately, commercially
available nickel-molybdenum alloys which exhibited excellent corrosion
properties were not well suited to contemplated reactor systems because
of three adverse characteristics: (l) poor fabricability; (2) a tendency
to age-harden and embrittle at service temperatures between 650 and
815°C (ref. 10); and (3) poor resistance to oxidation by air at elevated
temperatures. The scale formed on exposure of these alloys to high-
temperature air was of the type NiMoO,, which upon thermal cycling
between 760 and 350°C underwent a phase transformation and spalled as a
consequence of a resultant volume change.ll
By means of an alloy development program, however, it was considered
plausible to eliminate the undesirable features of the commercial materials
while retaining their inherent corrosion resistance. The initial objec-
tive of this program was to provide an alloy which did not embrittle under
the thermal treatments imposed by reactor operation. By experimenting
with various compositions of binary nickel-molybdenum alloys, 1t was
determined that lowering the molybdenum concentration to a level of 15-17%
served to avoid detrimental age-hardening effects in the alloy system.12
Although such an alloy system was satisfactory from the standpoint of
corrosion resistance, it was necessary to augment the oxidation and
strength characteristics of the system through additional solid-solution
alloying agents. The corrosion effects which resulted from these addi-
tions were the subjects of the present study.
1R, E. Clausing, P. Patriarca, and W. D. Manly, Aging Characteristics
of Hastelloy B, ORNL-2314 (1957).
iy, Inouye, private communication.
127, W. Stoffel and E. E. Stansbury, "A Metallographic and X-ray
Study of Ni Alloys of 20-30 Per Cent Mo," Report No. 1 under Subcontract
No. 582 under Contract No. W-7405-eng-26, Knoxville, Tenn., Dept. of
Chem., Eng. of the Univ. of Tenn. (1955).
MATERIALS AND PROCEDURES
Test Materials
The nickel-molybdenum alloy compositions selected for study were
supplied by the Metals and Ceramics Division at ORNL and, under subcon-
tract agreements, by Battelle Memorial Institute and Superior Tube
Company. Alloys furnished by ORNL were induction-melted under vacuum,
while those furnished by subcontractors were induction-melted in air
using a protective slag. Each alloy heat, which ranged in weight from
12 to 100 1b, was either forged or extruded into a 3-in.-diam tube blank
and was subsequently drawn into 1/2-in.-0D seamless tubing by the
Superior Tube Company. The cold-drawn tubing was annealed at 1120°C.
Table 2 lists the experimental alloy compositions used for this corrosion
study.
Test Eguipment
The method selected to evaluate the corrosion properties of these
alloys was based on the following considerations:
1. The method necessarily had to be tailored to the use of rela-
tively small quantities of material, since it was practical to produce
only small heats of the many alloys desired for study.
2. Tubing was considered to be a highly desirable form in which to
test the material, since production of the material in this form was
carried out as an adjunct to evaluating the fabricability of each alloy.
3. Previous demonstrations of the effects of temperature gradient
in the salt and the salt flow rate on the corrosion behavior of container
materials in fluorides made it mandatory that corrosion tests be con-
ducted under dynamic conditions, that is, conditions which provided for
the continuous flow of salt through a temperature gradient.
The thermal convection loop, which had been used extensively for
Inconel corrosion studies and had been developed into an extremely
straightforward and reliable test device, was judged to be the best form
of experimental device for meeting these requirements. This device con-
sists of a closed loop of tubing, bent to resemble the outline of a harp,
Table 2.
Compositions of Experimental Alloys Used for Corrcsion Studies
Composition, wt %
Composition, at. %
Heat
i
Number Wi Mo Cr Fe Ti Al Wb W v Ni Mo Cr Fe Ti Al Nb W v
Series T
OR 30-1 80.12 16.93 2.83 85.50 11.10 3.41
-2 78.55 16.65 4.62 83.60 10.80 5.55
-4 73.65 16.37 9.21 78.30 10.60 11.04
-6 78.50 15.11 .40 g82.70 9.72 7.60
37A-1 77.0 20.39 2.62 83.30 13.50 3.20
43A-3 73.30 20.34 6.34 78.90 13.40 7.71
Series IT
OR 30-7 82.10 15.93 1.88 85.60 10.15 4.26
-8 80.30 17.80 1.89 85.90 11.60 2.47 _
-9 81.10 16.8 .09 88.10 11.20 0.72
-10 81.10 16.60 2.23 86.40 10.80 2.73
-11 79.80 16.53 3.68 85.10 10.80 4,12
-12 80.00 16.80 3.22 86.70 11.10 2.20
-19 79.00 16.90 4 .10 g87.10 11.40 1.44
-20 79.20 16.60 4,18 84.10 10.80 5.11
=21 78.90 16.40 471 85.50 10.90 3.62
S T23012 82.00 17.42 0.53 87.40 11.40 1.22
OR 1491 86.58 11.23 2.19 88.16 6.99 4. 85
Series ITL
OR 30-13 79.93 17.56 1.56 0.95 84.48 11.35 2.02 2.18
=14 79.53 16.50 1.52 2.45 82.11 10.42 1.92 5.51
=16 77.74 16.00 3.65 1.49 1,12 81.01 10.20 4.30 1.90 2.54
-22 77.65 15,90 5.69 1.16 0.60 80.27 10,05 6.64 2.6l 0.39
-33 74.07 15.15 5.C1L 5.07 0,70 77.26 9.66 5,90 5.56 1.59
B2897 76.13 20,50 1.25 1.32 83.61 13.77 1.68 0.92
B2898 76.30 20.50 2. 44 1.31 82.60 13.20 3.24 0.90
B3276 69,12 21,10 7.58 2.16 75,17 14,00 9,32 1.48
B3277 66.95 21.60 7.82 1.31 2.32 7L.72 14.20 9.4%7 3.06 1.57
S T23011 71.50 15.06 3.84 0,83 4.17 4.90 79.04 10.20 4.79 1.27 2.91 1.72
S T23013 74.42 15.20 0.58 4.57 5.23 g83.14 10.36 1.40 3.23 1.85
S T23014 80.86 16.70 2,19 0.57 85.22 10.76 2.71 1.30
®0R denotes heats furnished by the Metals and Ceramics Division; 8 T by Superior Tube Company; and B by Battelle
Memorial Institute.
10
two legs of which are heated and two of which are exposed to the cooling
effects of ambient air. Flow results from the difference in density of
the salt in the hot and cold portions of the loop.
The configuration and dimensions of the loop design are presented
in Fig. 1. All loops were fabricated of seamless tubing having an out-
side diameter of 0.500 in, and a wall thickness of 0.035 in. The tubing
was assembled by the Heliarc welding technique using an inert gas
backing.
During operation the loops were heated by a series of clamshell
resistance heating elements located as shown in Fig. 1. To fill the
loop required that we apply heat to both the cold- and hot-leg sections.
Auxiliary heating for this purpose was provided by passage of electric
current directly through the tube wall. When the loop was filled, as
determined by an electrical shorting probe near the top of the loop, the
auxiliary heat source was turned off and the heating elements were turned
on. Insulation was then removed from the cold leg to whatever amount
was required to establish a predetermined temperature gradient.
Loop temperatures were measured with Chromel-P—Alumel thermocouples
located as shown in Fig. 1. The thermocouple junctions, in the form of
small beads, were welded to the outside tube wall with a condenser dis-
charge welder and covered by a layer of quartz tape, which in turn was
covered with stainless steel shim stock. All tests were operated so as
to achieve a maximum mixed-mean salt temperature of 215°C and a minimum
salt temperature of 65C°C. The maximum salt-metal interface temperature,
which was attained near the top of the vertical heated section, exceeded
the maximum bulk salt temperature by approximately 95°C (ref. 13). The
salt-flow rate under these temperature conditions was established from
heat balance calculations to be in the range of 5 to 7 ft/min,
13Measurements of the maximum inside wall temperature could not
practically be made in each loop test; however, values of this tempera-
ture were recorded by means of heat balance calculations and imbedded
thermocouples using a specially instrumented test loop which exactly simu-
lated the geometry and temperature profile used in the corrosion
experiment.
11
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Fig. 1. Schematic Diagram of Thermal Convection Loop Used for
Evaluations of Experimental Nickel-Molybdenum Alloys. The locations of
thermccouples and test samples are shown.
12
Salt Preparation
The fuel mixture used in these studies was of the composition shown
in Table 3. We selected the LiF-KF-NaF-UF, composition (Salt 107) on
the basis that the oxidation of container constituents by a given con-
centration of UF; tended to be greater for this mixture than for other
mixtures of practical importance. Thus, achievement of satisfactory
compatibility with this mixture in effect provided a container material
of ultimate versatility with respect to all fuel mixtures.
Table 3. Composition of Fluoride Mixture
Used to Evaluate Experimental
Nickel-Molybdenum Alloys
Salt Number: 107
Liquidus Temperature: 490°C
Component Mole % Weight %
NaF 11.2 9.79
LiF 45,3 24 .4
KF 41.C 49, 4
Uy, 2.5 16.3
The fluoride mixtures were prepared from reagent-grade materials
and were purified by the Fluoride Processing Group of the Reactor Chemistry
Division. In general, the procedure for purification was as follows:
(1) the dry ingredients, except for UF,, were mixed, evacuated several
times for moisture removal, and then melted under an atmosphere of helium;
(2) the molten mixture was held at 815°C and treated with hydrogen for 4 hr
to purge hydrofluoric acid from the mixture; (3) the mixture was cooled to
205°C under a helium atmosphere and UF, was admitted. Upon the addition
of the UF,, the mixture was remelted, heated to 815°C, and then treated
again with hydrogen to purge the excess hydrofluoric acid.
All mixtures were prepared in 300-1b gquantities and apportioned into
50-1b containers, after which samples were submitted for analysis of
Ni, Fe, and Cr. It was required that each of these elements be present
13
in amounts less than 500 ppm as determined from individual batch analyses,
A second before-test analysis of each salt mixture was obtained from a
sample of the salt taken as it was being admitted to the test loop.
Operating Procedures
Fach loop was thoroughly degreased with acetone and checked for
leaks using a helium mass spectrometer. After thermocouples and heaters
were assembled and insulation was applied, the loop was placed in a test
stand, as shown in Fig. 2.
The salt charging pot was connected to the loop with nickel or
Inconel tubing, and both the loop and the charging pot were heated to
€50°C under a'dynamic vacuum of less than 50 p Hg. Helium pressure was
then applied to the charging pot in order to force the salt mixture from
the pot to the loop. After filling, scalt was allowed to stand in the
loop at 650°C for approximately 2 hr, so that oxides and other impuri-
ties would be dissolved from the container surface into the salt mixture.
This mixture was then removed, and a fresh salt mixture was admitted
from the fluoride charging pot. A helium cover gas under slight positive
pressure (approx 5 psig) was maintained over the salt mixture during all
periods of testing.
At the end of test, power to the loop was cut off and insulation
was stripped from the loop so as to freeze the salt mixture as rapidly
as possible.
Test Examination
Each loop was sectioned with a tubing cutter into approximately
6-in. lengths. Five Z2-in. sections were then removed from the loop posi-
tions indicated in Fig. 1 for metallographic examination. Two of the
remaining 6-in. sections, one from the hottest section of the loop
(specimen H) and one from the coldest section (specimen C), were obtained
for salt chemistry studies, and the remaining loop segments were held in
storage until all examinations of the loop were completed.
Salt removal was accomplished by heating each section in a small
tube furnace at 600°C in helium., The salt was collected in a graphite
-
»
" Fig. 2.
Stands.
(
15
crucible located below the furnace windings. The five 2-in, sections of
tubing were examined metallographically, and the salt samples were sub-
mitted individually for petrographic and chemical analyses. .If layers
of corrosion products were discovered on the tube wall, samples of the
tubing and salt contained in that section were also submitted for x-ray
diffraction examination.
RESULTS AND DISCUSSION
Alloying effects were evaluated in terms of both the corrosion
products entering the salt mixtures and the metallographic appearance of
the alloy after test. Results have been grouped in this section
according to the alloying element studied.
Chromium
Corrosion-Product Concentrations
Effects of chromium additions were examined in six ternary alloys
with chromium contents of 3.2 to 11.0 at. %. One loop of each of these
compositions was operated with Salt 107 for 500 hr under the test condi-
tions described above, The compositicns investigated and the attendant
concentrations of chromium ions in salt samples taken at the conclusion
of these tests are shown in Table 4. The extent of reaction between
chromium and fluoride constituents, as indicaked by the chromium ion con-
centrations, increased with the amount of chromium in the alloy. This
increase is illustrated graphically in Fig. 3, where the data are com-
114 15 It may be noted
pared with data for Incone and for pure chromium.
that the chromium concentrations of the salts were less than those for
Inconel loops operated under identical temperature conditions. A hori-
zontal line, which represents the chromium ion concentration at
4G, M. Adamson, R. S. Crouse, and W. D. Manly, Interim Report on
Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953, ORNL-2337
(1959),
17, D. Redman, ANP Quart, Progr. Rept. Dec. 31, 1957, ORNL-2440,
pp. 78-L82.
16
Table 4. Corrosion-Product Concentrations of Salts Tested with
Nickel-Molybdenum-Chromium Alloys
Alloy Composition Tegt Chromium Concentration in
Heat (at. %) : Salt Samples® (mole %)
Number Duration
(hr)
Cr Other Components Sample H Sample C Other
OR 37A-1 3.20 13.5 Mo, bal Ni 5C0 0.01%4 0.0180 ©.0213
OR 30-1 3.41 11.1 Mo, bal Ni 500 0.0222 0.0365 0.0291
OR 30-2 5.55 10.8 Mo, bal Ni 5C0 0.0375 0.0352 0.0376
OR 30-2 5.55 10.8 Mo, bal Ni 1000 0.0509 0.0509 0.0543
OR 30-6 7.60 9,72 Mo, bal Ni 500 0. 0606 0.0606 0.0566
OR 43A-3 7.71 13.4 Mo, bal Ni 500 0.0453 0.0476 0.0425
OR 30-4 11.04 10.6 Mo, bal Ni 5C0 0.0819 0.0814 0.0699
®Sample designations "H" and "C" are discussed on page 13; "other"
designates salt samples obtained from metailographic specimens.
equilibrium with pure chromium at 600°C, is seen in Fig. 3 to be above
the measured chromium ion concentrations for all alloys tested. Thus,
the observed concentrations were less than those required for the forma-
tion of pure chromium crystals in the coldest portion of the loops
(approx 650°C).
As discussed previously, the concentration of chromium ions under
the conditions of these tests should be governed by the relation
[Eq. (11)]
N . = _ 5/19
Cr ions (NCI'F2 * NCI"F3) - K2CYC£ 3
where NCr sons is the mole fraction of chromium ions in Salt 107 at
equilibrium with an alloy of given chromium activity, o, . If we assume
Cr
op? the resultant chromium ion
concentrations for these alloys should lie within a region which is
that NCr giveg an approximate measure of &
bounded above by the function determined at a temperature equivalent to
the maximum loop temperature and below by the function determined at the
minimum loop temperature. Bounds using experimental values of K
17
ORNL—LR—DWG 46946