Combined gettering and molten salt process for tritium recovery from lithium

Sze, D.K.; Finn, P.A.; Bartlit, J.R.; Tanaka, Satoru; Teral, T.; Yamawaki, M.

doi:10.1016/s0920-3796(89)80128-0

Cited by 13 publications

(2 citation statements)

References 12 publications

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“…Given the impact of the tritium recovery efficiency upon the safety and sustainability of the fuel cycle, we have conducted a detailed assessment of possible alternatives. Several options have been evaluated based on previous studies and available literature, including permeable windows [21][22][23], gettering process [24,25], cold trap [26][27][28], distillation [29][30][31][32], molten salt extraction [33][34][35][36][37], and combination of gettering and molten salt extraction [38]. Based on a pre-conceptual functional requirements analysis, the molten salt extraction method was selected as primary candidate due to its capability to achieve lower inventories, moderate energy requirements, low estimated capital cost and faster dynamic response.…”

Section: Tritium Breeding and Extractionmentioning

confidence: 99%

Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

Reyes

Anklam

Meier

et al. 2016

Fusion Engineering and Design

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Over the past five years, the fusion energy group at Lawrence Livermore National Laboratory (LLNL) has made significant progress in the area of safety and tritium research for Inertial Fusion Energy (IFE). Focus has been driven towards the minimization of inventories, accident safety, development of safety guidelines and licensing considerations. Recent technology developments in tritium processing and target fill have had a major impact on reduction of tritium inventories in the facility. A safety advantage of inertial fusion energy using indirect-drive targets is that the structural materials surrounding the fusion reactions can be protected from target emissions by a low-pressure chamber fill gas, therefore eliminating plasma-material erosion as a source of activated dust production. An important inherent safety advantage of IFE when compared to other magnetic fusion energy (MFE) concepts that have been proposed to-date (including ITER), is that loss of plasma control events with the potential to damage the first wall, such as disruptions, are non-conceivable, therefore eliminating a number of potential accident initiators and radioactive in-vessel source term generation. In this paper, we present an overview of the safety assessments performed to-date, comparing results to the US DOE Fusion Safety Standards guidelines and the recent lessons-learnt from ITER safety and licensing activities, and summarize our most recent thoughts on safety and tritium considerations for future nuclear fusion facilities.

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Section: Tritium Breeding and Extractionmentioning

confidence: 99%

Recent developments in IFE safety and tritium research and considerations for future nuclear fusion facilities

Reyes

Anklam

Meier

et al. 2016

Fusion Engineering and Design

View full text Add to dashboard Cite

show abstract

“…Actualmente, el sistema de extracción de la sal fundida es un proceso en elección [57,58,59] y aunque se han probado en laboratorios los diferentes pasos del proceso de extracción, nunca se han demostrado a gran escala [60]. Es más, ninguna investigación implementando a la vez todos los pasos que se han explicado anteriormente se ha llevado a cabo para probar la viabilidad de la extracción de T. Además, existen algunas incertidumbres sobre cómo afectaría el método de extracción a la comportamiento y composición química del Li [61].…”

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