Showing papers by "Jacopo Buongiorno published in 2004"
TL;DR: The isotope 210Po is the main product of neutron activation in fast reactors cooled by molten lead-bismuth eutectic (LBE) and is a pure alpha emitter with a half-life of 138.38 days as discussed by the authors.
Abstract: The isotope 210Po is the main product of neutron activation in fast reactors cooled by molten lead-bismuth eutectic (LBE). The isotope 210Po is a pure alpha emitter with a half-life of 138.38 days....
31 citations
TL;DR: In this article, the authors outline the strategy and constraints adopted for the design of medium-power lead-alloy-cooled actinide-burning reactors that strive for a lower cost than accelerator-driven systems and for robus...
Abstract: We outline the strategy and constraints adopted for the design of medium-power lead-alloy–cooled actinide-burning reactors that strive for a lower cost than accelerator-driven systems and for robus...
30 citations
TL;DR: In this article, a multi-year project at Idaho National Engineering and Environmental Laboratory and the Massachusetts Institute of Technology investigated the potential of medium-power lead-alloy-cooled technology to perform two missions: (1) the production of low-cost electricity and (2) the burning of actinides from light water reactor (LWR) spent fuel.
Abstract: A multiyear project at the Idaho National Engineering and Environmental Laboratory and the Massachusetts Institute of Technology investigated the potential of medium-power lead-alloy-cooled technology to perform two missions: (1) the production of low-cost electricity and (2) the burning of actinides from light water reactor (LWR) spent fuel. The goal of achieving a high power level to enhance economic performance simultaneously with adoption of passive decay heat removal and modularity capabilities resulted in designs in the range of 600-800 MW(thermal), which we classify as a medium power level compared to the lower [{approx}100 MW(thermal)] and higher [2800 MW(thermal)] power ratings of other lead-alloy-cooled designs. The plant design that was developed shows promise of achieving all the Generation-IV goals for future nuclear energy systems: sustainable energy generation, low overnight capital cost, a very low likelihood and degree of core damage during any conceivable accident, and a proliferation-resistant fuel cycle. The reactor and fuel cycle designs that evolved to achieve these missions and goals resulted from study of the following key trade-offs: waste reduction versus reactor safety, waste reduction versus cost, and cost versus proliferation resistance. Secondary trade-offs that were also considered were monolithic versus modular design, active versus passive safety systems, forcedmore » versus natural circulation, alternative power conversion cycles, and lead versus lead-bismuth coolant.These studies led to a selection of a common modular design with forced convection cooling, passive decay heat removal, and a supercritical CO{sub 2} power cycle for all our reactor concepts. However, the concepts adopt different core designs to optimize the achievement of the two missions. For the low-cost electricity production mission, a design approach based on fueling with low enriched uranium operating without costly reprocessing in a once-through cycle was pursued to achieve a long operating cycle length by enhancing in-core breeding. For the actinide-burning mission three design variants were produced: (1) a fertile-free actinide burner, i.e., a single-tier strategy, (2) a minor actinide burner with plutonium burned in the LWR fleet, i.e., a two-tier strategy, and (3) an actinide burner with characteristics balanced to also favor economic electricity production.« less
24 citations
TL;DR: In this paper, a linear elastic seismic analysis for the vessel of a heavy-liquid-metal reactor was undertaken based on the Design Response Spectrum (DRS) approach and for a 0.5 g earthquake.
10 citations
TL;DR: In this paper, a power conversion cycle selection is a very important step in the design of a nuclear Reactor, due to the higher core outlet temperature (˜550°C) compared to that of light water reacto...
Abstract: Proper selection of the power conversion cycle is a very important step in the design of a nuclear reactor. Due to the higher core outlet temperature (˜550°C) compared to that of light water reacto...
9 citations
TL;DR: As a water-cooled nuclear system with a direct thermal cycle, the supercritical-water -cooled reactor (SCWR) shares with the boiling water reactor (BWR) the issue of coolant activation and transport as mentioned in this paper.
Abstract: As a water-cooled nuclear system with a direct thermal cycle, the supercritical-water–cooled reactor (SCWR) shares with the boiling water reactor (BWR) the issue of coolant activation and transport...
3 citations