Environmental Engineering Reference
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(a)
1200
EC316LN
1000
10.7
3.6
2.5
800
0.5 dpa
1.1
Unirrad.
600
400
200
0
0
10
20
30
Elongation, %
40
50
60
(b)
500
Mild Steel
10 19 n/cm 2
1.4
400
2.010 18
300
2.810 17
3.910 16
Unirradiated
200
￿ ￿ ￿ ￿ ￿ ￿
100
0
12
24
36
48
Elongation (%)
1. 14 (a) Effect of neutron irradiation on stress vs strain curves for
stainless steel (FCC) depicting the occurrence of yield points following
radiation exposure. 21 (b) Effect of neutron irradiation on stress vs
strain curves for mild steel (BCC) depicting the absence of yield points
following high neutron radiation exposure. 22
where
t ). The stress-strain curves shown in Fig. 1.14b on mild
steel at room temperature as a function of fl uence reveal that the yield
strength varied as cube-root of fl uence (Fig. 1.15) and not the square-root.
This seems to stem from the fact that friction hardening (
Φ
is fl uence (
φ
σ
i ) indeed varied
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