ICONE11-36405 FUEL CYCLE OF BREST REACTORS : Solution of the RW and non-proliferation problems

Orlov, V. V.; Lopatkin, A. V.; Glazov, A.G.; Volk, V. I.; Poluéktov, P. P.; Leontyev, V. F.; Karimov, R.S.

doi:10.1299/jsmeicone.2003.170

Cited by 2 publications

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“…Works on the development of lead-cooled fast reactors are actively carried out in Russia (technical design and planned construction of BREST-OD-300, work on the concept design of MN fuel BREST-1200 is underway [27,29]), European Union countries (concept projects ELFR, ELSY, LEADER, ALFRED with MOX fuel have been developed since 2006 [30]), and the USA by 2005-2007, and conceptual projects of STAR series of reactors of different target purpose with UN-fuel have been proposed [22,30].…”

Section: Modern Directions Of Development Of Power Lmfrsmentioning

confidence: 99%

Accident Tolerant Materials for LMFR

Okunev¹

2021

Nuclear Materials

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Several concepts of fast reactors with liquid metal coolant (LMFR) are being developed in the world. Lead-cooled reactors are most preferred for the safe nuclear power of the future. Projects of such reactors are being developed in Russia (BREST), the European Union (the latest development is ALFRED), and the USA (a series of STAR low-power reactor designs). The potential capabilities of fuel, coolant, and structural materials considered for use in the core to increase safety have not been exhausted. There are still unused reserves that can significantly increase the self-protection of the reactor. This chapter presents the results of the analysis of the use of new types of nuclear fuel: based on ceramics and beryllium and ceramics and uranium nanopowder. Studies are being conducted on the possibility of optimizing the composition of lead coolant without isotope separation. The possibilities of improving the safety of LMFR with a coolant based on lead extracted from thorium ores are being investigated. The possibility of using tungsten coatings of the cladding of fuel pins deposited using low-temperature plasma spraying is analyzed. The composition of materials was optimized in terms of improving reactor safety. The proposed innovations will significantly increase the self-protection of the reactor from the totality of severe accidents.

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Section: Modern Directions Of Development Of Power Lmfrsmentioning

confidence: 99%