OAK RIDGE NATIONAL LABORATORY

operated by
UNION CARBIDE CORPORATION
for the
U.S. ATOMIC ENERGY COMMISSION

ORNL- TM- 1017
S0

 

TENSILE AND CREEP PROPERTIES OF INOR-8 FOR

e ¢ il a4 bt S8 o oyt e
. - G

THE MOLTEN-SALT REACTOR EXF;ERIMENT

J. T. Venard

NCE OBTAINED. ggfiig 10
PUBLIC 1S APPROVED. \:R? EOURES

WRE ON FILE IN THE RECE!

NOTICE This document contains information of a preliminary 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 a final report.
 

 

 

LEGAL NOTICE

 

This report was prepared os an account of Government sponsored work, Neither the United States,

nor the Commission, nor any person acting on beholf of the Commission:

A. Makes any warranty or representation, expressed or implied, with respect to the accuracy,
completensss, 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

8. Assumes any liabilities with respect to the use of, or for damages resulting from the use of
any informatijon, apparatys, method, or process disclosed in this report,

As used in the above, '‘person acting on behalf of the Commission®’ includes any empioyee or

contractor of the Commission, or employee of such contracter, to the extent that such employee

or contractor of the Commission, or omployee of such contractor prepares, disseminates, or
provides access to, any infermation pursuant to his employment or contract with the Commission,

or his employment with such contractor.

 

 

[N

 

|
ORNL-TM~1017

Contract No. W-7405-eng-26

METALS AND CERAMICS DIVISION

TENSILE AND CREEP PROPERTIES OF INOR-§ FOR
THE MOLTEN-SALT REACTOR EXPERIMENT

J. T. Venard

FEBRUARY 1965

OAK RIDGE NATTONAL ILABORATORY
Oak Ridge, Tennessee
operated by
UNION CARBIDE CORPORATION
for the
U.5. ATOMIC ENERGY COMMISSION
TENSILE AND CREEP PROPERTIES OF INOR-8 FOR
THE MOLTEN-SALT REACTOR EXPERIMENT

 

 

J., T. Venard

ABSTRACT

Tensile and creep<rupture testing has been carried out on
three heats of INOR-8 selected from those used for the Molten-
Salt Reactor Experiment construction. The primary aim was to
develop strength information representative of the reactor
construction material and to compare the data on these commer-
cial heats with that from early experimental heats.

The data reported are ultimate tensile strength, 0.2% off-
set yield strength, percent elongation, and percent reduction
in area vs temperature from room temperature to 982°C (1800°F).
Creep-rupturg behavior was investigated at 593, 704, and 816°C
(1100, 1300, and 1500°F).

In general, the commercial MSRE construction material shows
greater strength and ductility than did earlier heats of the

alloy. Additional confidence in the MSRE design strength values

is thus in order.

INTRODUCTION

The decision to build the Molten-Salt Reactor Experiment necessitated
the procurement of some 100 tons of INOR-8 (Ref. 1). Since some minor
chemistry changes had been made to ensure weldability in these commercial
heats? and because of a desire to have strength information representative
of MSRE construction material, a series of tensile and creep tests were
performed.

Three heats of material were selected from the 27 heats used in the
reactor. This material was used for tensile tests in the range of 21°C
(70°F) to 982°C (1800°F). Creep-rupture tests were performed at 593,
704, and 816°C (1100, 1300, and 1500°F).

 

1Designated as Hastelloy N by Stellite Division of Union Carbide
Corporation and as INCO-806 by the International Nickel Company.
°R. G. Gilliland and G. M. Slaughter, Influence of Minor Alloying

 

Additions in INOR-8 Welds. Paper presented at Annual Meeting of American
Welding Society, Philadelphia, Pa., April 22-26, 1963. (To be submitted
to the Welding Journal).

 

 
MATERTAT, AND SPECIMENS

The alloy INOR-8 was developed especially for use in molten-salt
systems.3 The following tabulation gives the nominal composition of

this alloy.

 

Element dehtPfl@am4
Nickel Balance
Molybdenum 15.00-18.00
Chromium 6.00-8.00
Iron 5.00
Carbon 0.04-0.08°
Manganese 1.0
Silicon 1.0
Tungsten 0.50
Aluminum + Titanium 0. 50
Copper 0.35
Cobalt 0.20
Phosphorus 0.015
Sulfur 0.020
Boron 0.010
Vanadium 0.50

The three heats of material selected for testing were in the form
of plate. Their compositions are given in Table 1. Note that there is
little difference in the composition of the three heats. The major
differences are in the chromium, iron and manganese content of heat 5075.
Metallographically, the three heats of material look quite the same,
as is seen 1n Figs. 1 through 3. Note the stringers of precipitated

material which are aligned with the plate rolling direction. This kind

of structure is typical of this alloy in the wrought condition.

 

37, K. Roche, The Influence of Composition Upon the 1500°F Creep-

 

Rupture Strength and Microstructure of Molybdenum-Chromium-Iron-Nickel-
Base Alloys, ORNL-2524, (June 24, 1958).

 

4Single values are maximum percentages.

20.02 to 0.08 for pipe and tubing is included.
Teble 1. Chemical Analysis From Certified Test Reports

 

Composition (wt %)

 

 

Designation Ni Mo Cr Fe C Mn Si W Al Ti Cu Co P S B Vv

Heat 5055 Bal 16.20 7.86 3.76 0.06 0.69 0.61 0.03 0.06 0.02 0.01 0.10 0.006 0.008 0.005 0.21
Heat 5075 Bal 16.14 6.76 4.03 0.06 0.42 0.59 0.04 0.01 0.01 0.01 0.08 0.003 0.007 0.001 0.28
Heat 5081 Bal 16.87 7.43 3.35 0.07 0.55 0.60 0.03 0.01 0.01 0.02 0.07 0.001 0.006 0.004 0.26

 
 

 

 

 

 

 

 

 

Fig.

3.

As-Received INOR-8 Heat 5081.

 

 

 

Btchant: aqua regia.

 

 

v

O

¥

S

+ ,

g -

 

 
The specimens for the test program were cut both parallel and normal

to the plate rolling direction. A drawing of the specimen is shown in

Fig. 4.

ORNL—-DWG £4-7808

e s

«225+oom‘fl¢" '

=l

“1—— ?/8 %5/8

 

. |
(Tm—— ’W@ ) oém5+oomm
- R

   

/
y /"1/8 R
f'y@—wa THD
DIMENSIONS IN INCHES
Fig. 4. Creep and Tensile Specimen, INOR-8.

TESTING METHODS AND RESUITS
All tensile tests were run in a 12,000-1b capacity Baldwin Hydraulic
Stress-strain

In the

Testing Machine at a crosshead speed of 0.05 in./min.
curves were obtained through load cell-deflectometer outputs.
cage of elevated-temperature tests, 1/2 hr was allowed for the specimen
to reach equilibrium before loading was begun.

Average tensile data for heats 5075 and 5081 are shown in Table 2.

Two specimens of each heat were run at every temperature.

 

 

 

Table 2. Average Tensile Properties for INOR-8, Heats 5075 and 5081
Tempera- Ultimate Tensile 0.2% Offset Reduction of
ture Strength Yield Strength Elongation Area
(cc) (°F) (psi) (psi) (%) (%)
21 70 113,600 46,500 53.1 54.0
315 600 103,300 36,000 55.0 50.0
427 800 100, 100 35,000 53.3 52.5a b
538 1000 96,000 33,200 53.3a b 46.5a 52.0b
649 1200 74,800 32,600 22.0a 35.8b 27.9a 35.8b
760 1400 61,800 31,800 21.0 30.5  22.8 29.8
871 1600 36,400 31,600 23.0% 39.8° 4.2 43.0P
982 1800 20,300 20,000 27.9 28.9
Heat 5075
b

Heat 5081
Creep tests were run in Arcweld Lever Arm Testing Machines and strain
data obtained through dial-gage extensometers asttached to the specimen
shoulders.

Detailed tabulations of the creep-rupture test results are given in

Tables 3, 4, and 5.

DISCUSSION OF RESULTS

The tensile properties of heats 5075 and 5081 are plotted in Figs. 5,
6, 7, and 8. These figures show ultimate tensile strength, 0.2% offset
yield strength, elongation, and reduction of area vs temperature. The
scatter bands for experimental heats of INOR-& shown in these figures
were developed from data generated some time ago.6’7

The ultimate and yield strengths show no significant variation with the
heat tested nor did they vary with specimen-plate orientation. The
ductility values, however, indicate that above approximately 53&°C
(1000°F) heat 5075 is less ductile than heat 5081.

Creep and rupture curves plotted as log time to reach a total strain
of 0.2, 0.5, 1.0, 2.0, znd 5.0% and log time-to-rupture vs log stress are
given in Figs. 9 through 17. The elongation at fracture for each test is
noted by the numbers in parentheses.

Comparison of the various creep ductility values show that, as in
the tensile tests, heat 5075 was less ductile than the other heats tested.

A stress-rupture plot for all three heats is shown in Fig. 18. The
results for heats 5055 and 5081 have been fitted with a single curve, while
heat 5075 chows a somewhat lower rupture strength., It should be pointed
out that the weakest of these heats, heat 5075, is as strong as the strong-
est experimental heats previously reported.6

It is interesting to note from Fig. 19, which plots log minimum

creep rate vs log stress, that the creep rates of all three heats are

the same,.

 

®R. W. Swindeman, Mechanical Properties of INOR-8, ORNL-2780,
(Jan. 10, 1961).

 

7R. W. Swindeman, Unpublished Data in Private Communication to

J. T. Venard, January, 1963.
Table 3. Creep and Rupture Data for INOR-8 Tested in Adr>

 

 

 

Minimum
Test Creep

Test Temperature Stress Time to Reach Strain Ievel (hr) Rate Elongation at
Number (°C) (°F) (psi) 0.2% 0.5% 1.0% 2.0% 5.0% Rupture (hr 1) Fracture (%)
2267 593 1100 81,000 0.80 5.1 7.8 x 1073 37.2
2262 593 1100 70,000 0.10 0.15 0.20 0.40 32.2 33.5 6.5 x 1074 19.6
2248 593 1100 61,000 0.50 2.0 14.0 53.0 140.4 2.2 x 107+ 4.6
2201 593 1100 50,000 10.0 18.0 40.0  100.0 875 1040.7 2.3 x 10 % 6.2
1833 593 1100 35,000 500 1800 3350 5350 9325 9818.7 2.6 x 10 © 5.4
2273 704 1300 52,000 0.10 0.40 1.6 6.2 3.5 % 10 ° 29.8
2264 704 1300 39,000  0.20 1.0 2.7 6.2 13.8 29.8 3.4 x 10 3 16.1
2254 704 1300 34,000 0. 50 2.5 5.2 11.0 26.2 68.3 1.9 x 102 15.9
2246 704 1300 31,000 2.0 5.0 12.0 25.0 64.0 160.3 7.8 x 104 38.0
1840 704 1300 27,500 4.0 14.0 30.0 60 144 346.7 3.5 x 10 % 29.1
2200 704 1300 25,000 5.0 15 30 60 160 859.7 3.0 x 104 50.3
2144 704 1300 22,000 5.0 14 34 75 185 526.4 2.6 x 10 % 14.9
1982 704 1300 20,000 10 30 95 210 530 1707.3 9.4 x 1073 26.8
1842 704 1300 18,000 5 70 160 400 950 2682.2 5.0 x 10 % 25.0
2274 816 1500 23,000 0.1 0.3 0.6 1.2 3.0 13.9 1.8 x 10 ? 48.0
2272 816 1500 15,000 1.0 4.0 6.0 11 22 93.5 2.8 x 1073 42.9
2253 816 1500 12,500 1.0 4.0 8.0 16 42 189.0 1.2 x 1073 33.7
2239 816 1500 10,500 1.0 5.0 20 40 120 390.9 4.2 x 104 23.2
2188 816 1500 8,200 2.5 5.0 40 120 340 909.1 1.5 x 10 % 20.5
2263 816 1500 5,600 56 250 550 1250 3500 7593.8 1.1 x 10 3 20.1
1986 816 1500 5,600 100 280 660 1660 2377.1% 9.0 x 1074

 

aSpecimens of heat 5055 cut parallel to plate rolling direction.

Discontinued.
Table 4. Creep and Rupture Data for INOR-8 Tested in Air-

 

 

 

Minimum
Test Creep
Test o Temperature Stress Time to Reach Strain Level (hr) Rate Elongation at
Number  (°C)  (°F) (psi) 0.2% 0.5% 1.0% 2.0% 5. 0% Rupture (hr 1) Fracture (%)
3142(P) 593 1100 64,000 0.1 0.3 0.8 6.7 8.9 6.0 x 10 4 13.9
3127(P) 593 1100 59,000 0.2 0.5 1.2 3.0 18.0 23.5 2.0 x 10 4 10.8
2547(T) 593 1100 55,000 0.2 0.3 0.6 1.2 75.0 78.6 5.0 X 10 ° 9.1
2427 (P) 593 1100 48,500 33.0 103 133 135 135.6 5.5 x 10 ° 7.8
2564 (T) 593 1100 47,000 40.0 130 200 203 205.5 3.5 x 10 ° A
2826(T) 593 1100 42,000 130 465 732 885.2 6.0 x 106 1.6
2782(P) 593 1100 39,000 250 625 732 749.5 3,0 x 1076 1.5
3097(T) 593 1100 31,000 400 1400 2600 3890 3927.0 1.6 x 10 ® 3.9
2082(T) 704 1300 35,000 0.3 2.0 bods 10.0 22.6 2.0x 10 3 4.8
2952(P) 704 1300 26,000 1.5 4.5 11.0 50.0 75.7 2.1 x 10 % A
2944 (T) 704 1300 23,000 2.0 10.0 25.0 60.0 133 135.3 1.3 x 10 % 5.2
2637(P) 704 1300 22,000 25.0 48.0  77.0 114 137.9 1.3 x 10 4 4.2
2997(T) 704 1300 18,500 1.0 6.0 67.0 193.0 451.0 491.2 8.3 x 10 ° 7.5
2998 (P) 704 1300 16,500 10.0 50.0 126 305 645 680.2 5.1 x 1072 7.5
2888(T) 704 1300 15,000 10.0 65.0 195 450 855 924.8 4.2 x 10°° 7.1
2783(P) 704 1300 14,000 10.0 150 350 750 1410 1505.1 2.6 x 10 ° 7.6
2951(P) 704 1300 13,000 10.0 100 300 820 1605 1698.8 1.8 x 10°° 7.6
3086(T) 816 1500 19,000 0.1 0.4 0.9 2.0 6.5 20.6 6.3 x 10 3 28.9
3025(P) 816 1500 12,000 0.5 2.0 4.5 11.5 35.0 148.6 1.3 x 103 23.9
2977(T) 816 1500 10,000 2.0 11.0 20.0  46.0 121 358.1 3.9 x 10 % 19.9
2565(P) 816 1500 7,200  15.0 45.0 90.0 185 385 486.4 5.8 x 10 ° 11.2
2948(T) 816 1500 6,700 1.0 45.0 105 230 555 1034.3 8.3 x 10°° 12.8
2892(P) 816 1500 4,900 40.0 105 360 930 2175 2757.4 1.9 x 10°° 10.0

 

aSpecimens of heat 5075,

b(P) indicates specimen cut parallel to plate rolling direction and (T) indicates specimen

cut transverse to plate rolling direction.
Table 5. Creep and Rupbure Data for INOR-8 Tested in Air~

 

 

 

Minimum
Test Creep
Test Temperature Stress Time to Reach Strain Level (hr) Rate Elongation at
Number  (°C) (°F) (psi) 0.2% 0.5% 1.0% 2.0% 5.0% Rupture  (hr 1) Fracture (%)
3137(T) 593 1100 74,000 0.1 0.2 0.3 0.6 16.0 24.1 1.4 x 102 28.7
3119(P) 593 1100 66,000 0.1 0.3 0.4 0.5 72.0 93.4 2.8 x 104 20.3
3105(T) 593 1100 63,000 5.0 22.0  46.0  88.0 121 122.9 2.1 x 1074 14.6
3103(P) 593 1100 57,000 0.1 0.4 340 377.5 3.5 % 1075 13.5
2478(P) 593 1100 52,000 20.0 75.0 220 425 602 609.4 3.0 x 1073 7.6
2466(T) 593 . 1100 50,000 786.2 1.8 x 10 ° 8.9
2571(P) 593 1100 46,000 400 800 1300 1612 1615.3 1.2 x 1072 7.0
2991(T) 704 1300 48,000 0.1 0.2 0.5 3.0 13.2 1.3 x 102 28.6
2958 (P) 704 1300 39,500 0.5 1.5 3.0 6.5 16.0 53.3 3.2 x 103 26.1
2943(T) 704 1300 28,500 2.0 9.0 19.0 39.0 92.0 150.9 5.1 x 10 % 12.8
2968 (P) 704 1300 25,500 5.0 20.0 42.0 g82.0 200 469.3 2.6 x 10 % 17.2
2559(T) 704 1300 20,500 10.0  40.0 80.0 175 460 1194.6 1.1 x 10 “ 23.2
1958(P) 704 1300 20,000 60.0 135 270 425 910 1152.1 3.7 x 1077 5.9
2900(P) 704 1300 19,300 10.0 50.0 120 280 735 1596.7 6.8 x 10°° 17.9
3067(T) 816 1500 21,000 0.2 0.8 2.0 5.0 25.2 9.0 x 1073 46,8
3072(P) 816 1500 16,000 0.5 1.0 2.5 5.5 12.0 52,8 4.3 x 10 2 38.2
3014(T) 816 1500 14,000 1.0 4.5 6.5 13.5 34.0 125.2 1.4 x 10 3 30.0
2976(T) 816 1500 11,000 2.0 6.0 15.0 35.0 95.0 422.8 5.1 x 10 4 35.8
2949(P) 816 1500 8,700 5.0 20.0 45,0 100 275 834.2 1.8 x 10 4 23.2
2575(T) 816 1500 8,000 5.0 30.0 65.0 145 385 1429.8 1.1 x 1074 20.3
3071(P) 816 1500 6,300 12.0 50.0 150 325 1330 4896.3 2.3 x 10°° 26.5

 

aSpecimens of heat 5081.

b(T) indicates specimen cut transverse to plate rolling direction and (P) indicates specimen
cut parallel to plate rolling direction.
TENSILE STRENGTH (1000 psi)

0.2% YIELD STRENGTH {1000 psi)

10

ORNL-DWG 64-4414R2
TEMPERATURE (°C)

 

 

 

   
  

 

 

 

 

0 100 200 300 400 500 600 700 800 900 1000
140 - T T T I T
= | i i ! | | ] l |
|
120 L 4~7i e
o i % _—~SCATTER BAND FOR
7% 4éééy)4//yéégy 4, &  EXPERIMENTAL HEATS
100 t-—— ~ g Z @’" e — ) i
o 7
77 O
o — o
i | 4
|
L ' A
60 —t+r — At — - —
HEAT 5075
APARALLEL TO R.D.
a0 | e NORMAL TO R.D. | i
|
HEAT 5084 |

o PARALLEL TO R.D. | |
vNORMAL TO R.D. |

 

 

 

 

 

0 200 400 600 800 1000 1200 1400 1600 1800
TEMPERATURE (°F)

Fig. 5. Ultimate Tensile Strength of MSRE INOR-8.

ORNL-DWG 64—4445R2
TEMPERATURE (°C)
0 t00 200 300 400 500 600 700 800 900 4000

o T T T T T T T

 

a
| i
60 L L ’ —— l
1

0 N R

7
| _~SCATTER BAND FOR

Sy, T
N . N

50

  
 
 

t
i
A

30 7

20 i e S

HEAT 5075 ; ]

4 PARALLEL TO R.D. ;

* NORMAL TC R.D. _ ’

I

|

 

e

 

10 1 * HEAT 5084
o PARALLEL TO R.D.

v NORMAL TO R.D.

O ! . ‘ : E |
0 200 400 600 800 1000 1200 4400 1600 1800
TEMPERATURE (°F)

 

 

 

Fig. 6. Two Percent Yield Strength of MSRE INOR-8.
ELONGATION (%)

20 t -

0

11

ORNL-DWG 64-4416R2
TEMPERATURE (°C)
100 200 300 400 500 600 700 800 900 1000

T T T 7]

" _-SCATTER BAND FOR
EXPERIMENTAL HEATS

 

  
 
 

 

  

 

 

 

 

 

 

 

 

 

 

HEAT 5075 Ty
A PARALLEL TC R.D.
e NORMAL TO R.D.

- HEAT 5081 a
o PARALLEL TO R.D. !
v NORMAL TO R.D.

I U | ,Wfi} ]
O 200 400 600 800 1000 1200 1400 1600 1800
TEMPERATURE (°F)

 

 

 

 

 

 

Fig. 7. Elongation in 2 in. of MSRE INOR-8.
REDUCTION IN AREA (%)

i2

ORNL-DWG 64-4417R
TEMPERATURE {°C)
0 100 200 300 400 500 600 700 800 900 1000
T T T T T r T |

 

 

  
   

_—-SCATTER BAND FOR
EXPERIMENTAL HEATS

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

,/// . /a
7 / 7
b
2/ . / 2/
30 .
HEAT 5075 A 0
: s PARALLEL TO R.D. 1 : /// // |
50 L— ®eNORMAL TO R.D. .. | ‘
| //’
HEAT 508f //47
o PARALLEL TO R.D.
v NORMAL TO R.D.
10 |~ | — e = T
|
O _ i - .
0 200 400 600 800 1000 1200 1400 1600 1800

TEMPERATURE (°F)

Fig. 8. Reduction of Area of MSRE INCR-8.
 

100 Lfi I T
80 -

 

 

40 °

STRESS (1000 psi)

N
O

OJ

 

Fig. 9. Creep and Rupture Data for MSRE INOR-8.

ORNL— DWG 64 4438R
1 7o0aec -

 

 

    
   

 

 

 

 

    

 

 

 

 

BO | —1 T (1300°F) ‘+'
et T HEAT 5055 T
60 1ttt L AIR *lr*
7 e M s
© 40 | Twx Q T
o | o ’ B ]
@) ooy
= — . ' +o—f b L1
- | L] (500 ||
v L 3 L_(27} J%
Y SR (251
5 I Y ' \.fi.Xl' !
! 0.5 *0 20 50 RUPTURE
L H‘ L LRI T
0.4 1.0 10 100 1000 10,000
TIME (hr)

Fig. 10. Creep and Rupture Data for MSRE INOR-8.
14

ORNL—-DWG 64—4444R

 

L
[

o
o
[(g)

   

 

HEAT 5055

 

AIR

i

 

|

a
'

 

 

{1sd 00O} SS3Y 1S

10 10Q 1000 10,000

1.

04

TIME (hr)

Creep and Rupture Data for MSRE INOR-8.

Fig. 11.

ORNL-DWG 64-443€ER

 

 

 

593°C
(1100°F)
HEAT 5075

 

{1sd OOOL) SS3HLS

AIR

10 il

      

|

 

 

10 100 1000 10,000

1.0

0A

TiME (hr)

Creep and Rupture Data for MSRE INCR-8.

12.

Fig.
STRESS (1000 psi)

STRESS (1000 psi)

100

o
o

N
O

H
O

no
C

10

Fig. 13.

40

no
o

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OR 1.0

-

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01 1.0

Fig. 14.

 

15

ORNL-DWG 64-4439R

704°C
(1300°F)
HEAT 5075
AIR

|
@) -
N4 (8) (7]

(8)
8) !
10 > RUPTURE

100 1000 10,000

TIME (hr)

Creep and Rupture Data for MSRE INOR-8.

ORNL—DWG 64-4442R

g16°C
{(4500°F)
HEAT 5075
AIR

_(29)
. < t
0.5 1.0 2.0 *5.0 RUPTURE

u(24)
20—

~ 10)

100 1000 10,000

TIME (hr)

Creep and Rupture Data for MSRE INOR-8.
STRESS (1000 psi)

STRESS {1000 psi)

  
 

 

 

 

 

 

 

 

 

   

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

 

16
e’
ORNL-DWG 64—4437R
100 .
8 (29) + -
60 Vi T i 14) (8).
-~ - 9
RS ‘ ; )”-(7 :
40 SR 0.5% 1.0 zjo\lRUPT‘iJRE .
| | T | 3 : |
593°C o . | |
20 (M00°F) T T S '
HEAT 5081
AIR
10
0.1 1.0 10 100 1000 10,000
TIME (hr})
Fig. 15. Creep and Rupture Data for MSRE INOR-8.
CRNL—-DWG 64—4440R
100 T T " T R R R ‘le
B L e Th (1300°F) |
60 o il EEH I } %;;iHEALIF?Om Jr—
- ; } ; _ . o . I ! i
-
(23) | “,
| TS UL
- 0.2% \ S - .
= | 1 05 1.0 2.0 50 RUPTURE
Lol R
10 L : i ] ] ;i i I A i g :
0.1 1.0 10 100 1000 10,000
TIME (hr)
Fig. 16. Creep and Rupture Data for MSRE INOR-8.
~
ol

STRESS (1000 psi)

STRESS (1000 psi}

  

ORNL-DWG 64-4443R

 

  

40
816 °C .
30 (1500°F) -
HEAT 5081
20 ‘
10
8
6 |
10| 20 5.0 |RYFTURE
4 .
0.1 1.0 10 1000 10,000
Fig. 17. Creep and Rupture Data for MSRE INOR-8.
ORNL-DWG €4-4418R
100 - T T

. 593°C (11D0°F
I 1
11

 

 

 

| :
SO 704sc (1300°F) |

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f 1 bt
bt
B16°C (1500°F) ™~
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e
101 L _do HEAT 5055  =-ri i~
=14 HEAT 5075 o
0 HEAT 5081 N
5 B t 1
_OPEN SYMBOLS - PARALLEL TO R.D.
CLOSED SYMBOLS-TRANSVERSE TO
ED_SYMBOLS-TRANSVERSE
} | |
b bl
Do
| ‘ o
f ! ] ‘ ! : i | Pl i
1 10 100 1000 10,000

TIME TO RUPTURE (hr)

Fig. 18. Stress-Rupture Behavior of MSRE INOR-8.
18

3 ORNL-DWG 64-4434R
{x 407

80

60 e
593°C
(1100°F)
40

—

o +

=
e 20
w)
w
w
o
’.—
w
10 ‘ i . INOR—8
8 4l AS RECEIVED-TESTED IN AIR
. : - MATERIAL FROM MSRE PLATE
6 - o HEAT 5055

HgngF); ’ & HEAT 5075
| . 0 HEAT 508
4 | . OPEN SYMBOLS ~PARALLEL TO R.D.
CLOSED SYMBOLS ~TRANSVERSE TO R.D

 

1078 10”3 10”4 1072 1072 10~!
MINIMUM CREEP RATE ( )

 

in
in.—hr

Fig. 19. Creep Behavior of MSRE INOR-&.

CONCTLUSIONS

These experiments on three heats of INOR-8 used in the MSRE construc-
tion can be summarized with the following conclusions:

1. The tensile properties are equivalent to those for earlier experi-
mental heats of INOR-8.

2. The three heats tested show no tensile strength variation with
plate orientation or with heat.

3. One heat (5075) exhibited somewhat less ductility at tempera-
tures above approximately 538°C {1000°F) compared with heats 5055 and 5081.
4. Rupture strength in creep for these 3 heats is somewhat better

than those for the earlier heats.
5. The minimum creep rate behavior of all three heats is the same.
Since the design of the MSRE was based on the data from earlier
experimental heats of INOR-8, it would appear that an extra measure of
confidence in the integrity of the INOR-8 components of the reactor

components is in order.

-
19

ACKNOWLEDGEMENTS

The author wishes to express his appreciation to the Graphic Arts
Department and the Metals and Ceramics Division Reports Office for their
help in preparing this document. The work of C. W. Walker, who ran the
creep experiments; C. W. Dollins, who ran the tensile tests; and

V. G. Iane, who helped prepare the data, is also appreciated.
1-2.

46,

10.
11.
12.

14.
15.
16.
17.
18.
19.
20.
21.
22,
23.
24
25.
20.
27.
28,
29.
30.
31.
32.
33.
34.
35.
36.
37.
38.
39.
40.
41,
42,
43.
4ty
45,
46.
47,
48,
49,
50-52.

Central Research Library 53,
ORNL — Y-12 Technical Library 54,
Document Reference Section 55,
Iaboratory Records 56.
ILaboratory Records, ORNL RC 57.
ORNL Patent Office 58.
G. M. Adamson, Jr. 59,
L. G. Alexander 60.
S. E. Beall 61.
C. E. Bettis 62.
E. S. Bettis 63.
D. S. Billington 64,
F. F. Blankenship 65.
G. E. Boyd 66,
A, T. Boch 67.
S. E. Bolt 68.
C. J. Borkowski 69,
E. J. Breeding 70-72.
F. R. Bruce 73.
0. W. Burke T4,
D. O. Campbell 75.
S. Cantor 76.
W. G. Cobb 77
J. A, Conlin 78.
W. H. Cook 79.
L. T. Corbin 80.
G. A. Cristy g1.
J. L. Crowley 82.
¥. L. Culler 83.
J. E. Cunningham 84 .
W. W. Davis 85.
J. H. DeVan 86.
C. W. Dollins 87.
R. G. Donnelly 88.
D. A, Douglas, Jr. 89.
E. P, Epler 0.
W. K. Ergen 91.
A. P. Fraas 2.
J. H Frye, Jr. 93,
C. H. Gabbard 94, .
W. R. Gall 95.
R. B. Gallaher %6—101.
R. G. Gilliland 102.
W. R. Grimes 103.
A. G. Grindell 104.
D. G. Harmon 105.
C. S. BHarrill 106.
M. R. Hill 107.

21

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