Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1565633 | Journal of Nuclear Materials | 2013 | 8 Pages |
Abstract
Cold worked austenitic stainless steel type AISI 316 is used as the material for fuel cladding and wrapper of the Fast Breeder Test Reactor (FBTR), India. The evaluation of mechanical properties of these core structurals is very essential to assess its integrity and ensure safe and productive operation of FBTR to very high burn-ups. The changes in the mechanical properties of these core structurals are associated with microstructural changes caused by high fluence neutron irradiation and temperatures of 673-823Â K. Remote tensile testing has been used for evaluating the tensile properties of irradiated clad tubes and shear punch test using small disk specimens for evaluating the properties of irradiated hexagonal wrapper. This paper will highlight the methods employed for evaluating the mechanical properties of the irradiated cladding and wrapper and discuss the trends in properties as a function of dpa (displacement per atom) and irradiation temperature.
Related Topics
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Nuclear Energy and Engineering
Authors
V. Karthik, RanVijay Kumar, A. Vijayaragavan, C.N. Venkiteswaran, V. Anandaraj, P. Parameswaran, S. Saroja, N.G. Muralidharan, Jojo Joseph, K.V. Kasiviswanathan, T. Jayakumar, Baldev Raj,