Development of graded Ni–YSZ composite coating on Alloy 690 by Pulsed Laser Deposition technique to reduce hazardous metallic nuclear waste inventory

A review on immobilization of phosphate containing high level nuclear wastes within glass matrix – Present status and future challenges

“…In fact, former Soviet Union came up with a new Na Al phosphate glass formulation for immobilizing its sulfate containing HLWs [89]. 27 Al-(MQ) MAS NMR spectroscopic analysis of aluminophosphate glasses showed that replacement of P O P bonds by Al O P linkages is principally responsible for the improved chemical durability of the matrices [90]. The idea of employing phosphate glasses for waste immobilization was once again tried by United States, and this time it yielded good results in terms of conditioning Na and sulfate rich mixed waste from Solar Evaporation Basin of Hanford ( [91]; Table 4).…”

“…and crypto-crystalline (glass ceramics based on sphene, zirconolite, monazite, zircon, etc.) matrices [12][13][14][15][16][17][18][19][20][21][22][23][24] have been proposed but the final selection of wasteform materials depends on several scientific and technological merits and demerits associated with HLW compositions [25,26], product durability factors, processing constraints [27][28][29][30][31][32][33], service condition demands [34,35], etc. Thus identification of a suitable wasteform for any given HLW is a difficult task, and too much of expectations in terms of its long term performance within geological repository make the selection procedure even tougher.…”

“…Sengupta / Journal of Hazardous Materials 235-236 (2012)[17][18][19][20][21][22][23][24][25][26][27][28] …”

Photoluminescence study on irradiated yttria stabilized zirconia

“…Yttria (Y 2 O 3 ) stabilized zirconia (ZrO 2 , YSZ) is one of the most extensively studied oxide ceramic material, having numerous applications in the fields of bio-ceramics, fuel cells, sensors, nanomaterials, thermal/diffusion barrier coatings, and nuclear waste management [1][2][3][4][5][6][7][8][9][10][11][12]. In nuclear industry, cubic zirconia is considered as a potential inert host matrix for incineration of excess plutonium (Pu) [13][14][15][16][17][18] and transmutation of transuranic nuclear wastes [19][20][21][22].…”

Microstructural studies on Alloy 693

“…To avoid such situations, 'preventive management strategy', either through development of diffusion barrier coating on Alloy 690 or through its compositional modification appear to be more appropriate ones. Towards the first option, the authors have already successfully developed (i) Ni-YSZ composite [17] and (ii) Ni-aluminide [18] coatings on the laboratory scale specimens. However, considering the harsh environment experienced by the Superalloy within vitrification furnaces, it is thought worthwhile to explore the alloy modification route as well [19,20].…”