IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
IGCAR : Annual Report - Indira Gandhi Centre for Atomic Research
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IGC<br />
<strong>Annual</strong> <strong>Report</strong> 2007<br />
Rupture life,h<br />
1000<br />
Ti/C<br />
4 5 6 7 8 9 10<br />
973 K<br />
100<br />
0.16 0.20 0.24 0.28 0.32 0.36 0.40<br />
Titanium, wt%<br />
250 MPa<br />
200 MPa<br />
175 MPa<br />
Fig.2 Influence of titanium on creep<br />
rupture life of D9I SS (phosphorous =<br />
0.025 wt%, silicon = 0.75 wt% and<br />
carbon = 0.04 wt %).<br />
Ti/C ratio is considered an<br />
important parameter to assess<br />
the influence of titanium. From<br />
Fig. 2, it is seen that Ti/C ratio<br />
of 5.5 to 6 provides maximum<br />
creep strength in D9I SS<br />
containing 0.025 wt%<br />
phosphorous and 0.75 wt%<br />
silicon. The variation of<br />
minimum creep rate with<br />
titanium content also showed a<br />
minimum value corresponding<br />
to 0.22 to 0.24 wt% titanium<br />
(Fig. 3). Creep rupture ductility<br />
generally decreased with<br />
increase in titanium content.<br />
Minimum creep rate, s-1<br />
250 MPa<br />
200 MPa<br />
175 MPa<br />
10 -8 973 K<br />
10 -9<br />
10 -10<br />
0.20 0.25 0.30 0.35 0.40<br />
Titanium, wt%<br />
(b)<br />
Fig.3 Influence of titanium on<br />
minimum creep rate of D9I SS<br />
(phosphorous = 0.025 wt%, silicon =<br />
0.75 wt% and carbon = 0.04 wt %).<br />
III.C.2. Effect of Titanium on the Void Swelling<br />
Behavior in (15Ni-14Cr)-Ti Modified Austenitic Steels<br />
Studied by Ion Beam Simulation - Step Height and<br />
Positron Lifetime Studies<br />
One of the important property<br />
changes caused by irradiation<br />
in the fast reactor structural<br />
materials is void swelling. The<br />
dimensional changes<br />
introduced by void swelling<br />
limits the lifetime of structural<br />
components used in a reactor.<br />
There<strong>for</strong>e, resistance to void<br />
swelling is a major<br />
consideration in the choice of<br />
materials <strong>for</strong> the core<br />
components. The titanium<br />
modified steels exhibit greatly<br />
improved swelling resistance<br />
under breeder reactor<br />
conditions and consequently,<br />
have become a prime<br />
candidates <strong>for</strong> structural<br />
applications. Titanium modified<br />
(15Ni, 14Cr) steel and its<br />
improved versions with<br />
phosphorous additions<br />
(designated as D9 and D9I) are<br />
envisaged <strong>for</strong> use as fuel<br />
cladding and wrapper materials<br />
in Indian fast breeder reactor<br />
(FBR) programme. Accelerated<br />
heavy ions which have the<br />
inherent advantage of<br />
producing high displacement<br />
rates have been used <strong>for</strong><br />
evaluating the effect of minor<br />
alloying elements.<br />
The void swelling behavior of<br />
two steels: (A) (15Ni-14Cr)-<br />
0.25Ti and (B) (15Ni-14Cr)-<br />
0.15Ti were studied using<br />
heavy ion irradiation <strong>for</strong><br />
understanding the influence of<br />
titanium in the void swelling<br />
resistance of the alloys .The<br />
cold worked samples were preimplanted<br />
with a uni<strong>for</strong>m<br />
helium concentration of 30<br />
appm. This was followed by a 5<br />
MeV nickel ion irradiation to<br />
create a peak damage of ~<br />
100 dpa at damage rate of 7<br />
x10 -3 dpa/s at various<br />
irradiation temperatures<br />
between 700 and 970 K. The<br />
gross swelling in the specimen<br />
R&D FOR FBRs 45