Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964 Page: 65
xvi, 166 p. : ill. ; 28 cm.View a full description of this report.
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65
The influence of strain rate at elevated temperatures was investi-
gated, and these data are given in Table 4.2. The effect of irradiation
increases with decreasing strain rate. Figure 4.4 indicates that the ef-
fect of irradiation on the uniform elongation and true fracture strain may
reach a maximum at a temperature that is strain rate sensitive.
UNCLASSIFIED
ORNL-DWG 64-4008
4.2
--- UNIFORM STRAIN
-- FRACTURE STRAIN
=.0 0.2 (min)-4 HEAT 5084 C
4.00
O
U 0.8
0
z
3 0.6
z
H
cr-
S0.4
F-0.2
0-
400O
O
LU
0
-J
-J
0
HLU1
W
Q
[
r
Z
Q
Z
O
t-
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z
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F-IRRADIATION 'NN
TEMPERATURE .
500 .600 700 800 900
DEFORMATION TEMPERATURE (OC)Fig. 4.4. Effect of Irradiation
Elevated Temperatures.on the Ductility of INOR-8 at
The effect of postirradiation annealing on the elevated-temperature
problem has been investigated. Numerous investigations3 have shown that
postirradiation heat treatments in the range 950 to 110000 anneal the
damage causing embrittlement of stainless steel irradiated and deformed
at 20 to 1000C. Irradiated INOR-8 samples were given a 0.75-hr heat treat-
ment at 11750C prior to deforming at 700 and 9000C. The properties of the
irradiated alloy given the postirradiation heat treatment are compared to
those not heat treated in Table 4.3. The stability of the irradiation-
induced defect associated with the elevated temperature problem is remarka-
ble.
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Oak Ridge National Laboratory. Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964, report, July 1964; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc100344/m1/83/: accessed April 24, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.