“…Significant improvement in reactor performance and safety can be expected with MN-U fuel due to high density and thermal conductivity, equal role of Doppler reactivity coefficient in TOP WS and LOF WS, and neutron balance improvement (BRC = 1). By neutron balance and nature of emergency modes, MN-U fuel is close to U-Zr and U-Pu-Zr [11] but much higher temperature.…”
Section: Atf Based On Mn and Uranium Nanopowdermentioning
confidence: 97%
“…The results of these unique studies are published in [5][6][7][8][9][10]. Zirconium-doped metal fuel has been proposed as a possible accidenttolerant fuel for fast sodium reactors in the USA [11]. It is a high-density and heatconducting fuel.…”
Section: The History Of the Issuementioning
confidence: 99%
“…It is a high-density and heatconducting fuel. By the early 1990s, projects of modular sodium-cooled fast reactors PRISM and SAFR with such fuel were considered as promising in the USA [11,12].…”
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.
“…Significant improvement in reactor performance and safety can be expected with MN-U fuel due to high density and thermal conductivity, equal role of Doppler reactivity coefficient in TOP WS and LOF WS, and neutron balance improvement (BRC = 1). By neutron balance and nature of emergency modes, MN-U fuel is close to U-Zr and U-Pu-Zr [11] but much higher temperature.…”
Section: Atf Based On Mn and Uranium Nanopowdermentioning
confidence: 97%
“…The results of these unique studies are published in [5][6][7][8][9][10]. Zirconium-doped metal fuel has been proposed as a possible accidenttolerant fuel for fast sodium reactors in the USA [11]. It is a high-density and heatconducting fuel.…”
Section: The History Of the Issuementioning
confidence: 99%
“…It is a high-density and heatconducting fuel. By the early 1990s, projects of modular sodium-cooled fast reactors PRISM and SAFR with such fuel were considered as promising in the USA [11,12].…”
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.
“…In EBR-II, different axial contact locations for the assembly ducts as well as the looseness or tightness at these contact locations determined the sign of the reactivity feedback [26]. For smaller fast reactors such as EBR-II, fuel bowing is a dominant reactivity feedback effect.…”
Section: Reactivity Feedbacks Summarymentioning
confidence: 99%
“…BISTRO uses perturbation theory to calculate the delayed neutron parameters in six groups, the effective delayed neutron fraction, and mean neutron lifetime over the entire core. These values are given in Tables 25, 26 and 27 where β i is the delayed neutron fraction of the i th group, λ i is the delayed neutron half-life of the i th group and Λ is the mean neutron lifetime in the reactor.…”
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.