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

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

IGC<br />

<strong>Annual</strong> <strong>Report</strong> 2007<br />

IV.C.3. Application of Zircaloy-4 <strong>for</strong> Highly Corrosive<br />

Nitric Acid Environments in Reprocessing Plants<br />

Reprocessing of spent nuclear<br />

fuel used in FBRs involves use<br />

of nitric acid of high<br />

concentrations<br />

and<br />

temperatures <strong>for</strong> dissolvers and<br />

evaporators which are highly<br />

corrosive. The materials chosen<br />

<strong>for</strong> the fabrication of such<br />

reprocessing plant equipment<br />

should possess excellent<br />

corrosion resistance, ease of<br />

fabricability and reliability.<br />

Conventional austenitic<br />

stainless steels are not<br />

preferable in such highly<br />

oxidizing conditions as they<br />

undergo severe intergranular<br />

corrosion. Studies carried out<br />

earlier indicated good<br />

corrosion resistance of<br />

Commercially Pure Titanium<br />

(CP-Ti) and Ti-5%Ta as<br />

compared to AISI type 304L SS<br />

in highly oxidizing nitric acid.<br />

Thus, titanium was chosen <strong>for</strong><br />

fabricating electrolytic dissolver<br />

of CORAL plant, with a<br />

dissimilar joint by explosive<br />

joining process <strong>for</strong> linking to<br />

type 304L SS equipment in the<br />

plant, <strong>for</strong> reprocessing of spent<br />

fuel from FBTR. For future<br />

reprocessing plants, based on<br />

research and international<br />

experience, developmental<br />

ef<strong>for</strong>ts have been made <strong>for</strong> the<br />

fabrication of dissolvers by<br />

using Ti-5%Ta-1.8%Nb alloy.<br />

The excellent corrosion<br />

resistance of zirconium in nitric<br />

acid has been known <strong>for</strong> over<br />

50 years. Zirconium is highly<br />

resistant to nitric acid<br />

environments and is considered<br />

as candidate material <strong>for</strong><br />

various applications in spent<br />

nuclear fuel reprocessing plants<br />

involving highly concentrated<br />

nitric acid medium. Zirconium<br />

and its alloys are thus<br />

considered as candidate<br />

materials <strong>for</strong> various<br />

applications in spent nuclear<br />

fuel reprocessing plants<br />

involving nitric acid of high<br />

concentrations at high<br />

temperatures. Also, unlike<br />

titanium and its alloys,<br />

zirconium is unaffected by<br />

vapour and condensate of<br />

boiling nitric acid.<br />

An attempt was made to study<br />

the corrosion behaviour of<br />

Zircaloy-4 (Zr-with Sn-1.4%,<br />

Fig.1 (a) Corrosion rate of materials in three phase corrosion test, (b) Potentiodynamic polarisation curves of<br />

wrought and welded samples, in 11.5M HNO 3 medium.<br />

FUEL CYCLE 107

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

Saved successfully!

Ooh no, something went wrong!