Fast Reactor Technology for Energy Security: Challenges for Materials Development

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Fuel cycle cost of sodium cooled fast reactors is strongly dependent on the performance of core structural materials, i.e., clad and wrapper materials of the fuel subassembly, which are subjected to intense neutron irradiation during service, that leads to unique materials problems like void swelling, irradiation creep and helium embrittlement. In order to increase the burnup of the fuel and thereby reduce the fuel cycle cost, it is necessary to employ materials which have high resistance to void swelling as well as better high temperature mechanical properties. The Indian fast reactor program began with the commissioning of the 40 MWt Fast Breeder Test Reactors (FBTR). The core structural material of FBTR is 20% cold worked 316 austenitic stainless steel (SS). For the 1250 MWt Prototype Fast Breeder Reactor which is nearing completion of construction, 20% cold-worked alloy D9 (15Cr-15Ni-Ti) has been selected as the clad and wrapper material. The target burnup is 100 GWd/t. Advanced austenitic stainless steel called as IFAC-1 SS and oxide dispersion strengthened martensitic steels have been developed as future materials for achieving higher burnup. Type 316 SS and its modified versions are used as the major high temperature structural materials for out-of-core permanent components. Ferritic-martensitic steels are selected for steam generator applications. This paper reviews the unique problems in fast reactors and illustrates the global progress in developing advanced structural materials for fast reactors in the context of the Indian nuclear programme.

Fast Reactor Technology for Energy Security: Challenges for Materials Development

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