Development of cladding materials for sodium-cooled fast reactors in India

Baldev Raj, ; Ramachandran, Divakar ; Vijayalakshmi, M. (2009) Development of cladding materials for sodium-cooled fast reactors in India Transactions of the Indian Institute of Metals, 62 (2). pp. 89-94. ISSN 0972-2815

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Sodium-cooled fast reactors are an important component of India's move towards energy security. The Fast Breeder Test Reactor (FBTR) has been successfully operated for over 22 years, and the construction of a Prototype Fast Breeder Reactor (PFBR) has been taken up. Future development of Fast Reactor technology depends to a large extent on the economics, safety and waste management issues. The targets important for economics have been identified as reduction in capital costs, higher burn-up fuels, higher temperatures of operation, longer life and higher breeding ratios. These targets can be achieved with significant improvements in performance of materials, especially of Alloy D9 (15Cr-15Ni-0.2Ti), a titanium modified austenitic stainless steel, currently used for fuel cladding. Through research programmes implemented to improve the void swelling resistance of Alloy D9, it has been established that certain solute additions are essential in association with thermomechanical treatments for conferring swelling resistance. Research work conducted on refinement of Alloy D9 composition and thermomechanical treatments aimed at understanding irradiation effects, corrosion, mechanical properties and weldability at IGCAR Kalpakkam along with modelling studies for the prediction of weld behaviour is reported in the present paper. It is concluded that a significant rise in fuel burn-up can be achieved with the use of a new generation "InD9" alloy for fuel cladding.

Item Type:Article
Source:Copyright of this article belongs to Springer.
Keywords:Sodium-coled Fast Reactors; Grain Boundary Engineering; D9; Modelling: "Ind9"
ID Code:40508
Deposited On:24 May 2011 08:25
Last Modified:24 May 2011 08:25

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