In a nuclear facility,
the surface of stainless steels
(SS) was
found to be contaminated during the processing of radioactive liquid
waste. Their safe and secure disposal is highly challenging to the
nuclear industry. If the fundamental property of steel corrosion could
be evaluated, successful decontamination and effective decommissioning
strategies could be planned. Although individual radionuclide contamination
behavior on SS metal was studied, till date, SS contamination behavior
under the exposure of high-level liquid waste (HLLW) was unexplored.
In view of this, investigations were carried out to understand the
nature of contamination in SS 304L alloy under the exposure of simulated
HLLW (SHLLW). For understanding of radionuclide adsorption behavior
on structural materials, scanning electron microscopy/energy dispersive
X-ray spectroscopy and X-ray photoelectron spectroscopy have been
utilized for SS 304L. The solutions were analyzed using inductively
coupled plasma optical emission spectroscopy to calculate the changes
in the elemental composition of the solution and corrosion behavior
of SS. The passivation of SS coupons was observed in the presence
of HNO
3
due to enrichment of Cr at the surface. The deposition
of Cs and Mo was noticed, while SS coupons were exposed to SHLLW.
At 3 M HNO
3
and room temperature, the SS surface is mildly
passivated by Cr enrichment by formation of a Cr oxide layer on the
SS surface. However, the passive layer was not thick enough to attenuate
the signal from the substrate below the passivated layer. Hence, Fe
0
and Cr
0
were also found along with Cr
3+
and Fe
3+
(in small quantity). When temperature was elevated
to 70 °C, the SS surface was completely covered with the Cr oxide
layer, and hence no Cr
0
signal was observed. The small
signal of Fe
0
indicated that the signal from the substrate
surface is present below the passive layer. During the passivation
process, Cr diffused toward the passive layer, thereby producing a
Cr-depleted layer below the passive layer (Cr
0
signal was
not seen). In the case of SHLLW at 70 °C, the surface was fully
covered by Cr
3+
, Mo
6+
, and Cs
+
. Fe
and Ni were not observed at all. This finding will help to design
an effective corrosion inhibitor and suitable decontamination agent.
In addition to that, this information was found to be useful in designing
high-performance novel and modern age reactor materials with improved
characteristics.