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 />
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