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ORNL-TM-3321.txt
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107y
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CE!VED BY myyye
OAK RIDGE NATIONAL LABORATORY
operated by
UNION CARBIDE CORPORATION & NUCLEAR DIVISION
for the
U.S. ATOMIC ENERGY COMMISSION
ORNL- TM- 3321
THERMAL STABILITY OF TITANIUM~-MODIFIED
HASTELLOY N AT 650 AND 760° C
C. E. Sessions and E, E. Stansbury
AS
T CONF!RMEU
THS DO%UN%LASSW\ED 10N
DIVISION OFf LASSIFICA _
BY L a
NOTICE This document contains information of a preliminery nature
and was prepared primarily for internal use at the Oak Ridge National
Laboratory. It is subject to revision or correction and therefore does
not represent o final report.
e a e g ey gm TEREYTETTLN
NOFTEE ”:;:".-;;....:’35, » E:}“""‘""'I:";--
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fi!&fii’.mmm;‘& i - '
ROS8E
This report was prepared as an account of work sponscred 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,
M
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ORNL-TM-3321
" Contract No. W-7405-eng-26
METALS AND CERAMICS DIVISION
THERMAL STABILITY OF TITANIUM-MODIFIED o
HASTELLOY N AT 650 AND 760°C
C. E. Sessions and E. E. Stansbury
| ‘This - report’ was prepared as an account of work
-| ‘sponsored by the -United ‘States Government. Neither |-
1 the United States nor the United States Atomic Energy
| Ccommission, nor any of their employees, nor any qf _
-1 their contractors, subcontractors, or their -employees, |
| makes any warranty, express or implied, or assumes any
i .| legal Habllity -or responsibility for the sccuracy, com-
t | -pleteness of usefulness of any information, apparatus,
-1 product or process disclosed, or represents that its_usg
would not infringe privately owned rights. - -
-
- O JuLY 1971
OAK RIDGE NATIONAL LABORATORY
. Qak Ridge, Tennessee
.- - operated by :
_ UNION CARBIDE. CORPORATION
o for the
U.S. ATOMIC ENERGY COMMISSION
DTSTRIBUTION OF THIS DOCUMENT 1S
UKLIM
v
e s e —— i
u o . CONIENTS
v . Abstract . . . . . .. .. e e e e e e e e e,
Introduction . . . & v ¢ v v v e e e e e e e e e e e e e
Experimental PrOCEAUEE « + « + o o o o o o o o o o o o 0 e e
Results and Discussion e e e e e e e e e e e e e e e e e e e
Effect of Preaging on. the MEchanlcal Properties . . .-. e e e e
Effect of Aging on Ductlllty 4 e e e e e s e e e e e
Effect of Aging on the Strehgth .« e e e ; v e e e e e e
B OV N
Stress-Strain Curves . « v ¢« 4 ¢« « s 4 4 s s e s e e s e .. . 10
Comparison of Measures of Ductility . . « v v v ¢ v v . . ... 11
Room-Temperature Tensile ?ropertieS' c f e e e e e e
Creep Properties After 3000 hr of,Aglng Ce e
Effect of Preage Treatments s s e e e e e e e e e e e e
i
Effect of Aging Temperature s 4 s w b 4 e s 4 s 4 e s o e w
Effect Of Tltanlm . .. » - . . s . . - . - . .- . - . . . .
&)
Comparison of Tensile and Creep Results c e e e e e e ae e e
Results ofrUnaged Samples e e e e e ; e e d e e e
Results for Aged Samples . . . . . . . . . C S e e e e e
Phases Identified in Aged Alloys C e et e e e e e e
MEtallography e e e e e e e e e e e e e e e e e e e e .20
Initisl Microstruetures s 4 e s e 4 4 e s s s s e e e s« 20
Mlcrostructures Developed During Aglng C e e e e e e e e 20
STEERGGHGREKRK
;
Structures Developed in Prestrained Materlal'.f, . i e . . .23 . 3
Fracture of Samples Tested 1n Creep T o |
Summary and Conclu31ons S~
| | Appendlx C e e e e ':;lfi; ce e e e e e e .~. C e e .. .35
4
7%
" et
( o
f ~y i
o
§
L
'THERMAL STABILITY OF TITANIUM-MODIFIED
HASTELLOY N AT 650 AND 760°C
C. E. Sessions and E..E. Sté,nsbury1
ABSTRACT
We have investigated the influence of small titanium
~ additions on the thermal stability of Ni-12% Mo-7% Cr-0.07% C.
' The mechanical properties at 650°C (tensile tests at 0.002/min
strain rate and creep tests at 40,000 psi stress) were mea-
‘sured for four heats of this alloy'w1th titanium contents
from 0.15 to 1.2%. Solution annealing temperatures were 1177 -
“or 1260°C, and subsequent precipitation heat treatments were
conducted at 650 and 760°C. Titanium increases the stebility
of a complex MC-type carbide. At low titanium levels the
MC carbide is stable at 650°C but is unstable at 760°C, where
an MpC-type carbide is precipitated, resulting in inferior
properties. For the higher titanium concentrations the
MC carbide is stable on aging at 760°C and results in excel-
lent properties after a solution anneal at 1177°C. However,
high-titanium alloys are significantly less ductile if they
are solution amnealed at 1260°C and aged at either 650 or
760°C. The heat with the lowest carbon content (0.04% C)
was most resistant to property ‘changes on aglng up to
10, 000 hr at both 650 and 760 c.
INTRODUCTION
We are concerned'witfifmbdifying the composition of Hastelloy N for
better perfbrmance as a material for a mplten-salt thermal breeder reac-
. tor w1th an expected llfetlme of 30 years or more. The ex1st1ng
| Hastelloy N developed primarlly at Oak Ridge over the past 10 to
12 years functioned well in an 8-Mw(t) reactor built five years ago and
ff0perated over the past three years.2 However, this reactor operated at
' 1Consultant,fro:mthe Uhifiersity of Tennessee, Knoxville;VTennessee.
24, E. McCoy, Jr.; An Evaluation of the Molten-Salt Reactor Experi-
ment Hastelloy N Survelllance Specimens — Fourth Group, ORNIL~TM-3063
(March 1971) .
2
650°C, and-when it was construéted very littlé was known about the
problem of high-temperature irradia.tion da.ma.ge‘ to this alldy. Since
that time we have observed® damsage by thermal neutrons on meny mate-
rials, including nickel-base alloys such as Hastelloy N, in which a
larger deterioration in properties is observed than in most iron-base
alloys. -Thus , an alloy with greater resistance to radiation damage is
needed. )
. We found that small additions of reactive elements, notably tita-
‘nium, can significantly enhance the fiostirradiation'creep-rupture life
and ductility.4 Thus, we have proceeded with the development of &
modified Hastelloy N conteining titanium. This report represents the
phase of the program concerned .with the effect of thermal and mechani-
cal treatment on the creep and tensile behavior of these experiménta.l
a.lloys. ' a
EXPERIMENTAL PROCEDURE
The material investiga.ted: in this program was produced by & com-
mercial vendor. These four 100-1b heats wgi'e vecuum induction melted
with initisl ingot brea.kdown at 1177°C and final fabrication to 0.5-in.
plate at 870°C. The titanium content was the primary variable, being
0.15, 0.27, 0.45, and 1.20% as shown in Table 1. Although & nominal
carbon level of 0.07% was specified, the carbon content of Heat 466-548
wes lower than the others. The various thermal and mechanical treat-
ments epplied are given in Table 2. The variables include solution
annealing conditions, cold work, aging time, and aging temperature.
The dimensions of the mechanical property test specimen'are shown ' |
ianig. 1. This specimen was used so that the results could be t.:ompared.
directl_y to postirradiation mechanical pi-operty tests for which this
3H. E. McCoy, "Variation of the Mechanical Properties of Irradiated
Hastelloy N with Strain Rate,” J. Nucl. Mater. 31, 67-85 (1969).
- %H. E. McCoSr,‘ Jr., Influence of Titanium, Zirconium, and Hafnium
Additions on the Resistance of Modified Hastelloy N to Irradiation
Damage at High Temperature — Phase I, ORNL-TM-3064 (Januery 1971).
o
«}
1
L
C
~ Element
3
Table 1. Chemical Analyses of Alloys in Aging Program
466=535%
Chemical Analyses, wt %
466=541 L466-548 467-548
Mo 12.8 13.2 12.4 12.0
Cr 7.2 6.8 7.7 7.1
Ti 1 0.15 . 0.27 0.45 1.20
C 0.073 0.07 0.04 0.08
. Fe 0.03 . 0,03 0.03 0.04
Si 0.07 0.05 0.05 0.03
Mn 0.12 0.10 0.14% 0.12
Mg 0.034 0.01 0.023
W 0.007 0.07 0.007 0.004
Zr 0.0002 0.0007 < 0,0001 0.002
v < 0.01 - < 0.01 < 0.01 0.001
Co 0.02 - 0.04 0.03 0.15
Cu 0.002 0.005 0.0005 0.01
Nb- < 0.0001 - - 0.0001 - 0.0003 0.0005
Al < 0.03 < 0.03 < 0.03 0.05
s 0.003 - < 0,002 0.003 < 0.002
P , o : - - 0.0004
B 0.0002 . 0.0002 0.00007 0.0007
0 0.0012 0.0008 0.001 0.0003
N 0.007 0.0005 0.0009 0.0002
H 0.0002 0.0002 0.0002 0.0003
Ni Balance Balance Balance Balance
aHeat numbers of 100-1b heats obtained from the Stellite'Division
ion. - _
of the Cabot Corporat
Table 2. VariablesAConsidered in This Study
- Variable
Titanium content, %
Preage treatment -
Aging temperature, °C
- Aging time, hr o
Testing after aging
Tensile
. Creep
Levels or Treatments
0.15, 0.27, 0.45, and 1.2
;_;_Soiution ameal 1 hr at 1177°C
‘Solution anneal 1 hr at 1260°C
Anneal 1 hr at 1177°C, then pres
room temperature '
650 and 760
1500, 3000, and 10,000
- 650°C, 0.002/min strain rate
- ':_'__650'0_(;’_-.'40,'000_ psi stress -
train 10% at
ORNL-DWG €7-3013
£ £ €
£ g 88
3 g
= o
S N 63
c c° g8
|
0.250 in,
~ DIAM
N\_ 0187519990 R(TYP)
s—— 3/e in.——
1125 in, —
1% i,
Fig. 1. Mechanical Property Test Specimen.
specimen was designed. Specimens were solution annealed in.argon end
aged in stainless steel capsules that had been evacuated and backfilled
with argon. Conventional tensile measurements were carried out fising
an Instron tensile machined equipped with a specimen furnace. Two
Chromel-P vs Alumel thermocouples were used with a proportioning con-
troller to keep the test specimen Va.t 650 = 3°C.
The mitrostructures developed during aging were studied by optical
and electron transmission miecroscopy, extraction replication, and
scanning 'microscopy. In addition, precipitated phé,ses present in cer-
tain alloys were identified by x-rey diffraction using the Debye- |
Scherrer technique on precipitates extracted electrolytically with a
methanol-10% HC1l solfi;tion.r Details of the microstructure exsmination
have been répbi'ted,5 ‘and the alloying effects of titanium have been
summarized.® We shall concern ourselves here with the detailed mechani-
cal property response to heat treatment and a limited discussion of
’ miérostructures revealed in optica;l meta.llbgraphy.
3C. E. Sessions , Influence of Titanium-on the High-Temperature
Deformation and Fracture of Some Nickel Based Alloys, ORNL-4561
Tduly 1970).
6C. E. Sessions, E. E. Stansbury, R. E. Gehlbach, and
H. E. McCoy, Jr., "Influence of Titanium on the Strengthening of a
Ni-Mo-Cr Alloy," pp. 626—630 in Second International Conference on the
Strength of Metels and Alloys, Conf. Proc., Vol. 1I, The American Society
for Metals, Metals Park, Ohio, 1970.
A
)
N
"}
F 1)
C
Because of the large number of variables 1ncluded in this study
and the attempt to measure ‘the ccmplicated and very subtle differences
introduced by titanium.addltions, these experiments were statistically
designed as a full factorial replication7.including the variables in
Table 2. The purpose of this experimental design was to prcvide better
evaluation and separation’ofrthe'influence of the specific variables on
the tensile property response. Results of these statistical analyses
" have been discussed previously.®
RESULTS AND DISCUSSION
Typical results of the influence of preage thermal-mechanical
treatment, aging time, and temperature‘on the tensile and creep proper-
ties at 650°C will be presented first. The phase identification'will
then be presented and discussed in light of the mechanical property
changes. Strength and ductility values for all specimens tested are
given in’the Appendix;r | ' '
- Effect of Preaging:onrthe Mechanical Properties
Flgure 2 shows the yield strength (0 2% offset) and total elonga-
tion values for the three preage treatments investigated. Solution
annealing 1 hr at 1260° C lowered the strength and increased the ductil-
ity at each titanium level as compared to a l-hr solution anneal at
1177°C. Prestraining 10% at room temperature after allphr 1177°C solu-
tion anneal doubled the hlgh—temperature yield strength and reduced the
T{'ductility by one-third The yield strength increased'with titanium
content for these unaged specimens, but the tensile ductility was not
| appreciably affected by the titanium content for these pretest
treatments.
- TE. M. Bartee, Engineering Experimental Des1gn Fundamentals,
Prentice-Hall, Englewood Cliffs, N.J., 1968.
| 8C S. Lever and C. E. SeSS1ons Fuels and Materials Development
Quart. Progr. Rept. Sept. 30 1969, omso, Pp. 215-279.
3 ORNL-DWG 69-4761R2
{X10°) 45 : <
. - /l .
70 - . 40
thraTu?z7ecy /. | ‘ oA
10% PRESTRAIN/ ' _
. : 000
y.
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‘8 z o
£ 50 £ a0l |
g g . 77°C
& g / —* e AT Y
& 40 | W 25—y
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e ——
4 “wmwnPC+
. 10 % PRESTRAIN
20 15
10 ' ' 10
O 0.3 06 09 12 0 0.3 0.6 0.9 1.2
TITANIUM CONCENTRATION (%)
Fig. 2. Effect of Titanium Content and Preaging Treatments on the
Strength and Ductility of Modified Hastelloy N at 6570.°C
Effect of Aging on Ductility
Changes in tensile elongation with aging time are shown in Figs. 3
through 5 for both aging temperatures. Aging at either 650 or 760°C
after a solution anneal at 1177°C enhanced the ductility at 650° °C for
the 1.2% Ti heat and decreased it for the 0.15% Ti heat. After a l-hr
solution anneal at 1260°C, the 1.2% Ti heat lost ductility on aging at
either aging temperature to the same extent as did the 1owest-titanium
‘level, 0.15%. Thus, the larger grain size or greater‘amcunt'of 501ute
in solid solution after the 1260°C treatment maede the high-titanlum
heat susceptlble to a detrimental aging reaction to which it was immune
~ after the 1177°C anneal. ,
The effect of prestraining on the aging behavior is shown in
Fig. 5. Samples were solution annealed 1 hr at 1177°C, prestrained 10%
&t room temperature, aged at either 650 or 760°C, and then tested at
650°C. The verietion in tensile ductility with aging time and titanium
was similar to that shown in Fig. 3 for samples not prestrained; how-
ever, the overall ductility was lower for the prestrained material.
" ORNL-DOWG 69-4110
- : - ' ' - o . ORNL-DWG 69-4142
“ 1 11T 1 1 6° | |
ANNEALED. 4477°¢| . © ANNEALED t477°C ANNEALED 1260°C ANNEALED 1260°C
| ]acep AT 6s0°C AGED AT 760°C | AGED AT 650°C - AGED AT 760°C
' - 50
| leemTi - 2% Ti \\-.._3.45% Ti
2 1 - 0.45% T / : . _ fl
g | /| > - | | 1 11
-2 - . S | | . b :
e | - s s\ | 1| s Neashm ||
' :'5' . : ”o g 1.2% Ti : ' - _
20 _
... 20 — — v ' N ,
o kfio.fii_}'l \ o_qfl/b ) | : \\o ‘ \.....fi__ 0.145% Ti
) \A__ ] - 0.15% Ti | / e T—
vo b— | 10 —
0 - L e ‘ | %2 4 & 8 100 2 4 & 8 10
o 2 4. .6 '8 t00 2 4. 6 8 10 | AGING TIME {1000 hr)
- . AGING TIME (1000 hr) | | | -
Fig. 3. Effect of Titanium Content and Fig., 4. Effect of Titanium Content and
Aging Time on the Tensile Ductility at 650°C Aging Time on the Tensile Ductility at 650°C
‘after a l-hr Solution Anneal at 1177°C. after a l-hr Solution Anneal at 1260°C.
ORNL-OWG TO-13666R
BT
1.2%Ti
1.2% Ti
3
1 4
304 —+
\ <
25 :
> o.45% Ti :
0.45%Ti ANNEALED AT MTTC
- _ PRESTRAINED 10%
z ANNEALED 77°C AT 25%
) AGED AT 760°C
& zoj PRESTRAINED 10% — ,
£ AT 25°C ‘ {
S AGED AT 650°C
s 0.45% Ti
wd
Y s
.z_:‘ \
2 \ 0.15% Ti '
3
0.15% Ti ~o
10 \'-.j
T
,\ql
5
o
0 2 4 6 g8 10 0 2 4 6 8 10
AGING TIME (1000 hr)
Fig. 5. Effect of Titanium Content and Aging Time on the Tensile
Ductility at 650°C for Samples Solution Annealed 1 hr at 1177°C and Pre-
strained 10% at Room Temperature.
For aging at 650°C the intermediate (0.45%) and high (1.2%) titanium
heats showed an incresse in ductility with aging time. The low (0.15%)
titanium heat exhibited & rapid loss in hot duetility with aging tifie at
650°C. Aging at 760°C affected the ductility of the low- and high-
tité.nium heats the same as aging at 650°C , whereas the intermediate
(o. 45%) ‘titanium heat showed a ductility deterioration with time at
760°C in contrast to the ductility enhancement found after a.g:.ng at
650°C.
Eff'ect of Aging on the Strength
‘The changes in the yield strength on aging are shown for only the
- 1=hr solution anmneal at 1260°C in Fig. 6. For aging at both 650 and
.0
»
w)
a¥
C ’
ORNL-DWG 69-4441R
(x103)
1 ANNEALED 1260°C o ANNEALED 1260°C
AGED. AT 650°C AGED AT 760°C
. 50 : L. ’ :
| remmi 1.2% Ti
N
Q
=40 r — ._ 7
i | _0.512/15
| eeoimere™
2 /” f\ OA5%Ti
g 30 \l«_-..—-—-—!'—'—'—'!—‘—-_.iA
a M _ 045%TI | M 045% Ti