23.01.2014 Views

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

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

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

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!