Fusion Breeder Reactor Design Studies

Moir, R.W.; Lee, J. D.; Coops, M. S.; Fulton, Fred J.; Neef, W.S.; Berwald, D.H.; Campbell, R. B.; Flanders, B.; Garner, Joel H.; Ghoniem, N.M.; Ogren, J.; Saito, Yuko; Slomovik, A.; Whitley, R.H.; Schultz, K.R.; Benedict, G.E.; Cheng, E.T.; Creedon, R.L.; Maya, I.; Pierce, V.H.; Strand, J.B.; Wong, C.P.C.; Karbowski, Jan; Rose, R.P.; DeVan, J.H.; Tortorelli, P.F.; Miller, L.G.; Hsu, P.Y.; Beeston, J.M.; Hoffman, N.J.; Jassby, D.L.

doi:10.13182/fst4-2p2-589

Cited by 8 publications

(1 citation statement)

References 3 publications

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“…9,10 The majority of recent large-scale, well-developed fusion energy concepts use deuterium and tritium (D-T) as their fusion fuel and fit into two broad categories based upon how they achieve the conditions necessary for fusion reactions in the D-T fuel: ICF, in which neutral particle or ion beams directly or indirectly impart their energy upon the D-T fuel to create combined temperatures and pressures that support ample fusion reaction rates and confinement times in intermittent bursts, or magnetic confinement fusion involving electromagnetic systems that control ionic plasmas and heat them up enough to cause fusion reactions. As described in further detail below, the analyses performed for this work focused on FFHs using a solid-state laser-driven ICF concept.…”

Section: Ia Fusion-fission Hybridmentioning

confidence: 99%

Thorium Fuel Cycles with Externally Driven Systems

Brown¹,

Powers²,

Todosow³

et al. 2016

Nuclear Technology

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Section: Ia Fusion-fission Hybridmentioning

confidence: 99%

Thorium Fuel Cycles with Externally Driven Systems

Brown¹,

Powers²,

Todosow³

et al. 2016

Nuclear Technology

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Concept of a blanket first wall supported by radial tubes

Moir

1987

Fusion Engineering and Design

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Thermo-mechanical and neutron lifetime modelling and design of Be pebbles in the neutron multiplier for the LIFE engine

DeMange¹,

Marian²,

Caro³

et al. 2009

Nucl. Fusion

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Concept designs for the laser inertial fusion/fission energy (LIFE) engine include a neutron multiplication blanket containing Be pebbles flowing in a molten salt coolant. These pebbles must be designed to withstand the extreme irradiation and temperature conditions in the blanket to enable a reliable and cost-effective operation of LIFE. In this work, we develop design criteria for spherical Be pebbles on the basis of their thermo-mechanical behaviour under continued neutron exposure. We consider the effects of high fluence and fast fluxes on the elastic, thermal and mechanical properties of nuclear-grade Be. Our results suggest a maximum pebble diameter of 30 mm to avoid tensile failure, coated with an anti-corrosive, high-strength metallic shell to avoid failure by pebble contact. Moreover, we find that the operation temperature must always be kept above 450 °C to enable creep to relax the stresses induced by swelling. Under these circumstances, we estimate the pebble lifetime to be at least 16 months if uncoated, and up to six years when coated. We identify the sources of uncertainty on the properties used and discuss the advantages of new intermetallic beryllides and their use in LIFE's neutron multiplier. To establish Be-pebble lifetimes with improved confidence, reliable experiments to measure irradiation creep must be performed.

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Fusion Breeder Reactor Design Studies

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Cited by 8 publications

References 3 publications

Thorium Fuel Cycles with Externally Driven Systems

Thorium Fuel Cycles with Externally Driven Systems

Concept of a blanket first wall supported by radial tubes

Thermo-mechanical and neutron lifetime modelling and design of Be pebbles in the neutron multiplier for the LIFE engine

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