High-temperature reactors fuel development

Although the reductions in plant costs from the magnox to the AGR and high-temperature reactors have been and will continue to be important factors in the development of economic gas-cooled reactors in the power range of 500 to 1000 MWe, it is to be expected that future improvements in capital costs of very large plants will be less significant than possible improvements in fuel cycle economics. For example, the differ-... 

Tborium is tbe nuclear fuel resource available in India in plentiful quantities to sustain a large power programme. At present, tbe design and development of Advanced Heavy Water Reactor (AHWR) and Compact High Temperature Reactor (CHTR) are underway for utilization of tborium. Incorporation of simplified and passive systems is one of tbe features of these reactors. Tbe R D work related to these reactors is being carried out in BARC. 

Regarding the potential to share design and technology development with reactors of other types, a remarkable example is provided by the AHTR, a pre-conceptual system that is part of the U S. Department of Energy Generation IV reactor programme. About 70% of the R D required for the AHTR is shared with that for helium cooled high temperature reactors. This includes fuel development, materials development, and Brayton power cycles. Annex XXVI. 

About 70% of the R D required for the AHTR is shared with that for helium cooled high temperature reactors. This includes fuel development, materials development, and Brayton power cycles ... 

MSR developments in Russia on the Molten Salt Actinide Recycler and Transmuter aim to be used as efficient burners of transuranic waste from spent UOX and MOX LWR fuel without any uranium and thorium support and also with it. Other advanced reactor concepts are being studied, which use the liquid salt technology as a primary coolant for fluoride salt-cooled high-temperature reactors, and coated particle fuels similar to high-temperature gas-cooled reactors. 

The beginning of molten salt reactor (MSR) research in Korea dates back to 1998. A basic concept of an MSR that bums the DUPlC fuel was first developed in Ajou University. More studies on MSR, including a recent fluoride—salt-cooled high temperature reactor, are under progress in UNIST (Ulsan National Institute of Science and Technology) and other institutes. Described below is a summary of the progress so far and future research plans of the MSR research in Korea. 

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