Accident Tolerant Materials for LMFR

Abstract

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.

Fundamentally New Composite Materials of Fast Reactors Made on the Basis of Nanotechnology

“…With beryllium additives in the fuel, the risk of reactive accidents increases, and the risk of accidents with loss of coolant decreases. was performed using the FRISS program [13][14][15]. The results of the effect of beryllium additives on the maximum temperatures of MN fuel and coolant are presented in Fig.…”

“…Composite cermet tablet fuel based on fine-grained MOX and nanosized U. The technology proposed by the authors of [12] can be easily generalized to the manufacture of pellet-metalceramic MOX-U fuel based on fine-grained MOX and nanopowder U for BN-type reactors [8,13]. One of the advantages of using such fuel in the attainability of the conditions for the Breeding ratio in the core (BRC): BRC = 1.…”

“…The core of the BN-800 [16] and BREST-OD-300 [17] reactors was studied. The calculations were performed using the FRISS and DRAGON-M programs [13][14][15]. To increase the safety of the BREST reactor, it is necessary to increase the absolute value of the negative Doppler coefficient of reactivity [8,13,15,18,19].…”

“…The calculations were performed using the FRISS and DRAGON-M programs [13][14][15]. To increase the safety of the BREST reactor, it is necessary to increase the absolute value of the negative Doppler coefficient of reactivity [8,13,15,18,19]. In LOF WS mode, sodium boiling is possible when using MOX fuel.…”

“…In LOF WS mode, sodium boiling is possible when using MOX fuel. To increase the safety of the BN reactor, it is necessary to decrease the modulus of the negative Doppler reactivity coefficient [8,13,15].…”