Preliminary design study of the ultra long life fast reactor
References (11)
- et al.
Neutronic feasibility of an LMFBR super long-life core
Nucl. Engrg. Des.
(1988) - et al.
Non-refueling liquid metal fast breeder reactor
Trans. Am. Nucl. Soc.
(1979) - et al.
Interim liquid metal reactor and fuel cycle design options
Trans. Am. Nucl. Soc.
(1984) - et al.
The new liquid-metal reactor
Trans. Am. Nucl. Soc.
(1985) Physics considerations in the design of long life cores
Trans. Am. Nucl. Soc.
(1986)
Cited by (20)
An approach to quantifying the chemical conditions necessary to form a magnetite layer on steels in lead and lead-bismuth eutectic
2014, Journal of Nuclear MaterialsCitation Excerpt :% Bi) cooled nuclear technology is currently pursued worldwide under the framework of generation-IV nuclear programs and spallation neutron source development [1,2] (GIF LFR Provisional System Steering Committee). Active efforts backed by both public and private funding are pursued in the US [3–5], EU framework programs [6–9], Russia [10,11], Sweden [12,13], Italy [14], South Korea [15–17], Japan [18–21], India [22] and elsewhere. As a nuclear reactor coolant, lead and LBE offer significant advantages over other available alternatives.
The prospect of gas cooled fast reactors for long life reactors with natural uranium as fuel cycle input
2013, Annals of Nuclear EnergyCitation Excerpt :Such system needs high breeding/conversion ratio fuel to produce enough plutonium during its operation. High fuel volume fraction nitride fuel is chosen in this studies for such reason (Sekimoto and Su’ud, 1995; Su’ud and Sekimoto, 1993, 1995a; Su’ud, 2008). To obtain the capability of consuming natural uranium as fuel cycle input, modified CANDLE burn-up scheme (Su’ud and Sekimoto, 2010) is adopted in this GCFR system by dividing the core into 10 parts of equal volume axially.
Development of conceptual design tool for liquid metal cooled-reactors
1999, Annals of Nuclear EnergyAccident analysis of lead or lead-bismuth cooled small safe long-life fast reactor using metallic or nitride fuel
1996, Nuclear Engineering and DesignSafety aspect of long-life small safe power reactors
1995, Annals of Nuclear EnergyPerformance of Thorium Uranium Nitride (Th, U233)N Fuel for 500 MWth GFR Long-Life Without Refuelling use FIITB-CHI Code
2019, Journal of Physics: Conference Series