Hydrogen permeation through niobium membrane contacting with liquid lithium

Tanaka, Satoru; Katsuta, H; Furukawa, Katsuko; Kiyose, Ryohei

doi:10.1016/0022-3115(81)90418-9

Cited by 12 publications

(3 citation statements)

References 7 publications

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“…Tanaka, et al., measured hydrogen permeability of niobium contacting with liquid lithium [15] and found that the values are one to two orders of magnitude lower than anticipated from extrapolation of Rudd's data. This was explained by slow surface process wh'?…”

Section: Permeation Window Processmentioning

confidence: 96%

Combined gettering and molten salt process for tritium recovery from lithium

Sze¹,

Finn²,

Bartlit³

et al. 1989

Fusion Engineering and Design

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A new tritium recovery concept from lithium has been developed as part of the U.S./Japan collaboration on Reversed-Field Pinch Reactor Design Studies.This concept combines the y-gettering process as the front end to recover tritium from the coolant, and a molten salt recovery process to extract tritium for fuel processing. A secondary lithium is used to regenerate the tritium from the gettering bed and, in the process, increases the tritium concentration by a factor of about 20. That way, the required size of the molten salt process becomes very small. A potential problem is the possible poisoning of the gettering bed by the salt dissolved in lithium. DISCLAIMER

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Section: Permeation Window Processmentioning

confidence: 96%

Combined gettering and molten salt process for tritium recovery from lithium

Sze¹,

Finn²,

Bartlit³

et al. 1989

Fusion Engineering and Design

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“…The influence of impurities on hydrogen permeation has been illustrated with niobium in commercialgrade liquid lithium. The rate of permeation was reduced by 10 2 compared with the permeability in the absence of lithium and its impurities [44]. Thermally formed oxide films in 304 stainless steel reduced hydrogen permeability eight times at 986 K but, for >1050 K, the protection diminished and permeation rates increased with time, possibly because of reduction of the oxide film by hydrogen [45 ].…”

Section: Permeabilitymentioning

confidence: 96%

Chemical Aspects of Fusion Technology – 1982

1983

Nucl. Fusion

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The latest research results in the areas of tritium breeding materials properties, coolants, hydrogen isotope interactions with structural materials, tritium recovery cycles and plasma interactions with the first wall are reviewed. Areas where required information is currently lacking are identified, and specific recommendations are made for work which should be given priority in order to most rapidly advance the international effort in fusion technology. These areas include: liquid-metal/structural-alloy interactions (including magnetic-field effects), analytical techniques for low levels of tritium and impurities in breeder materials, tritium interactions with breeder and structural materials, thermochemistry and therm ophysical properties of solid breeder materials, corrosion product transport and deposition in magnetic fields, hot-water reactions with Lii 7 Pbs3 and ceramic breeding materials, tritium handling and recovery cycles, chemical reactions at the plasma/wall interface and impurity getters, and in-pile of pilot-scale tests of breeder materials, tritium interactions with structural materials and discharge cleaning of advanced first-wall materials.CONTENTS. 1. INTRODUCTION; 2. STATUS REVIEW: 2.1. Breeding materials; 2.1.1. Liquid metals; 2.1.2. Solid breeders; 2.1.3. Solubility of hydrogen in breeder materials; 2.2. Coolants; 2.3. Hydrogen isotope transport and related effects; 2.3.1. Permeability; 2.3.2. Embrittlement; 2.4. Tritium cycles; 2.5. Plasma/wall and limiter interaction; 2.5.1. Discharge cleaning of the first wall; 2.5.2. Chemical sputtering; 2.5.3. Recombination of atomic hydrogen and permeation; 2.5.4. Effect of radiation from plasmas on chemical processes at the first wall; 2.5.5. Impurity control in hydrogen; 2.6. General considerations on a power reactor tritium breeding blanket; 3.

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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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Hydrogen permeation through niobium membrane contacting with liquid lithium

Cited by 12 publications

References 7 publications

Combined gettering and molten salt process for tritium recovery from lithium

Combined gettering and molten salt process for tritium recovery from lithium

Chemical Aspects of Fusion Technology – 1982

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

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