Safety Assessment of the ARIES Compact Stellarator Design

Merrill, B.J.; El-Guebaly, L.; Martin, Carl J.; Moore, Richard L.; Raffray, A.R.; Petti, David A.

doi:10.13182/fst08-5

Cited by 28 publications

(7 citation statements)

References 28 publications

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“…A different 1D model based on radial permeation computation and simulating axial lead-lithium convection as gas transfer between enclosures has been proposed according to Merrill [10] as interesting alternative.…”

Section: Discussionmentioning

confidence: 99%

Optimizing tritium extraction from a Permeator Against Vacuum (PAV) by dimensional design using different tritium transport modeling tools

Martínez¹,

Moreno²,

Martínez

et al. 2012

Fusion Engineering and Design

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Section: Discussionmentioning

confidence: 99%

Optimizing tritium extraction from a Permeator Against Vacuum (PAV) by dimensional design using different tritium transport modeling tools

Martínez¹,

Moreno²,

Martínez

et al. 2012

Fusion Engineering and Design

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“…We have analyzed the ex-VV LOCA by using the fully integrated, engineering-level thermohydraulics analysis code MELCOR [44,45] with modifications for fusion reactor safety applications [46,47]. MELCOR is being used for several fusion reactor safety cases, for example ITER [47] and ARIES series [8,48].…”

Section: Accident Scenario Analysismentioning

confidence: 99%

Key Aspects of the Safety Study of a Water-Cooled Fusion DEMO Reactor

Nakamura

Tobita

Someya

et al. 2014

Plasma and Fusion Research

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Key aspects of the safety study of a water-cooled fusion DEMO reactor is reported. Safety requirements, dose target, DEMO plant model and confinement strategy of the safety study are briefly introduced. The internal hazard of a water-cooled DEMO, i.e. identification of hazardous inventories, identification of stored energies that can mobilize these hazardous inventories and identification of accident initiators and scenarios, are evaluated. It is pointed out that the enthalpy in the first wall/blanket cooling loops, the decay heat and the energy potentially released by the Be-steam chemical reaction are of special concern for the water-cooled DEMO. An ex-vessel loss-of-coolant accident (ex-VV LOCA) of the first wall/blanket cooling loop is also quantitatively analyzed. The integrity of the building against the ex-VV LOCA is discussed.

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“…This concept of the fixed transfer chamber has a safety advantage as providing a more secure containment barrier, as discussed in Ref. 13.…”

Section: Ivc Transfer Chamber Approach and Definitionmentioning

confidence: 99%