High performance blanket for ARIES-AT power plant

Raffray, A.R.; El-Guebaly, L.; Gordeev, S.; Malang, S.; Mogahed, E.A.; Najmabadi, F.; Sviatoslavsky, I.N.; Sze, D.K.; Tillack, M. S.; Wang, X

doi:10.1016/s0920-3796(01)00493-8

Cited by 65 publications

(29 citation statements)

References 2 publications

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“…12) Fusion power reactor design studies assume that SiC/SiC composites can be used in gas-cooled solidbreeding blankets [13][14][15][16] and helium/Pb-Li dual-coolant blankets. 17,18) Some of the dual-coolant blanket concepts, including the US-proposed Test Blanket Module (TBM) for the International Thermonuclear Experimental Reactor (ITER), utilize channel inserts made of SiC or SiC/SiC as an electrical and thermal insulator.…”

Section: Introductionmentioning

confidence: 99%

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

et al. 2005

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Fast fracture properties of chemically vapor-infiltrated silicon carbide matrix composites with Hi-NicalonÔ Type-S near-stoichiometric silicon carbide fiber reinforcements and thin pyrolytic carbon interphase were studied. The primary emphasis was on preliminary assessment of the applicability of a very thin pyrolytic carbon interphase between fibers and matrices of silicon carbide composites for use in nuclear environments. It appears that the mechanical properties of the present composite system are not subject to strong interphase thickness effects, in contrast to those in conventional non-stoichiometric silicon carbide-based fiber composites. The interphase thickness effects are discussed from the viewpoints of residual thermal stress, fiber damage, and interfacial friction. A preliminary conclusion is that a thin pyrolytic carbon interphase is beneficial for fast fracture properties of stoichiometric silicon carbide composites.

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Section: Introductionmentioning

confidence: 99%

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

et al. 2005

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“…While 7 MW/m 2 may certainly be possible, ARIES-AT blanket performance studies have shown maximum power loading of only 4.8 MW/m 2 on a silicon carbide (SiC) blanket [13]. Given this, it would not be prudent to let PF/AS exceed ~ 5 MW/m 2 [12].…”

Section: Blanket Fusion Power Density Pf/asmentioning

confidence: 99%

A fission-fusion hybrid reactor in steady-state L-mode tokamak configuration with natural uranium

Reed¹,

Parker²,

Forget³

2012

AIP Conference Proceedings

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The most prevalent criticism of fission-fusion hybrids is simply that they are too exotic -that they would exacerbate the challenges of both fission and fusion. This is not really true. Intriguingly, hybrids could actually be more viable than stand-alone fusion reactors while mitigating many challenges of fission. This work develops a conceptual design for a fission-fusion hybrid reactor in steady-state L-mode tokamak configuration with a subcritical natural or depleted uranium pebble bed blanket. A liquid lithiumlead alloy breeds enough tritium to replenish that consumed by the D-T fusion reaction. Subcritical operation could obviate the most challenging fuel cycle aspects of fission. The fission blanket augments the fusion power such that the fusion core itself need not have a high power gain, thus allowing for fully non-inductive (steady-state) low confinement mode (L-mode) operation at relatively small physical dimensions.A neutron transport Monte Carlo code models the natural uranium fission blanket. Maximizing the fission power while breeding sufficient tritium allows for the selection of an optimal set of blanket parameters, which yields a maximum prudent fission power gain of 7.7.A 0-D tokamak model suffices to analyze approximate tokamak operating conditions. If the definition of a "reactor" is a device with a total power gain of 40, then this fission blanket would allow the fusion component of a hybrid reactor with the same dimensions as ITER to operate in steady-state L-mode very comfortably with a fusion power gain of 6.7 and a thermal fusion power of 2.1 GW. Taking this further can determine the approximate minimum scale for a steady-state L-mode tokamak hybrid reactor, which is a major radius of 5.2 in and an aspect ratio of 2.8. This minimum scale device operates barely within the steady-state L-mode realm with a thermal fusion power of 1.7 GW. This hybrid, with its very fast neutron spectrum, could be superior to pure fission reactors in terms of breeding fissile fuel and transmuting deleterious fission products. It could operate either as a breeder, producing fuel for pure fission reactors from natural or depleted uranium, or as a deep burner, fissioning heavy metal and transmuting waste with a cycle time of decades. Despite a plethora of potential functions, its primary Mark Reedmission is deemed to be that of a deep burner producing baseload commercial power with a once-through fuel cycle. Although hybrids are often purported a priori to pose an elevated proliferation risk, this reactor breeds plutonium that could actually be more proliferation-resistant than that bred by fast reactors. Furthermore, a novel method (the "variable fixed source method") can maintain constant total hybrid power output as burnup proceeds by varying the neutron source strength.As for engineering feasibility, basic thermal hydraulic analysis demonstrates that pressurized helium could cool the pebble bed fission blanket with a flow rate below 10 m/s. The Brayton cycle thermal efficiency is 41%.This device is d...

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“…3 There are 12 side blanket modules in the reactor, each subtending 30 o of circumference. At midplane the major radius is 6.5 m but at the ends, it tapers down to 2.5 m. Each module is made up of 13 submodules, which vary in width and depth to accommodate the reduction in radius.…”

Section: Iib Description Of Side Blanketmentioning

confidence: 99%

A Lithium Self-Cooled Blanket for the HAPL Conceptual Inertial Confinement Reactor

Sviatoslavsky

Raffray²,

Sawan³

et al. 2005

Fusion Science and Technology

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High performance blanket for ARIES-AT power plant

Cited by 65 publications

References 2 publications

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

Mechanical Properties of Chemically Vapor-Infiltrated Silicon Carbide Structural Composites with Thin Carbon Interphases for Fusion and Advanced Fission Applications

A fission-fusion hybrid reactor in steady-state L-mode tokamak configuration with natural uranium

A Lithium Self-Cooled Blanket for the HAPL Conceptual Inertial Confinement Reactor

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