Conceptual design of Indian molten salt breeder reactor

@article{Vijayan2015ConceptualDO,
  title={Conceptual design of Indian molten salt breeder reactor},
  author={P. Vijayan and A. Basak and I. V. Dulera and K. K. Vaze and S. Basu and R. K. Sinha},
  journal={Pramana},
  year={2015},
  volume={85},
  pages={539-554}
}
The third stage of Indian nuclear power programme envisages the use of thorium as the fertile material with 233U, which would be obtained from the operation of Pu/Th based fast reactors in the later part of the second stage. Thorium-based reactors have been designed in many configurations, from light water-cooled designs to high-temperature liquid metal-cooled options. Another option, which holds promise, is the molten salt-fuelled reactor, which can be configured to give significant breeding… Expand
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