Tritium recovery from tritiated water with a two-stage palladium membrane reactor

Birdsell, Stephen A.; Willms, R.S.

doi:10.1016/s0920-3796(98)00144-6

Cited by 26 publications

(9 citation statements)

References 4 publications

(1 reference statement)

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“…The PCS separates two streams: the first one is rich in hydrogen isotopes and is treated afterwards in a Pd-Ag membrane diffuser and the second one is rich in He. processes [20][21][22][23][24]. Moreover, dense defect-free Pd membranes exhibit the complete selectivity of the hydrogen isotopes even at relatively low operating temperature (673 K), thus, attaining high detritiation rates [25].…”

Section: Tritium Extraction System For a Hcpb Breeding Blanketmentioning

confidence: 99%

“…Moreover, metal dense membranes demonstrate good stability, which is another important requirement for safe operation in the nuclear plant. Due to all these considerations, dense Pd-Ag membranes are currently the most used technology for separation processes in fusion fuel Processes 2016, 4, 40 3 of 13 cycles and have been extensively studied and applied in tritium recovery processes [20][21][22][23][24]. Moreover, dense defect-free Pd membranes exhibit the complete selectivity of the hydrogen isotopes even at relatively low operating temperature (673 K), thus, attaining high detritiation rates [25].…”

Section: Introductionmentioning

confidence: 99%

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Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

et al. 2016

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Abstract:Dense self-supported Pd-alloy membranes are used to selectively separate hydrogen and hydrogen isotopes. In particular, deuterium (D) and tritium (T) are currently identified as the main elements for the sustainability of the nuclear fusion reaction aimed at carbon free power generation. In the fusion nuclear reactors, a breeding blanket produces the tritium that is extracted and purified before being sent to the plasma chamber in order to sustain the fusion reaction. In this work, the application of Pd-alloy membranes has been tested for recovering tritium from a solid breeding blanket through a helium purge stream. Several simulations have been performed in order to optimize the design of a Pd-Ag multi-tube module in terms of geometry, operating parameters, and membrane module configuration (series vs. parallel). The results demonstrate that a pre-concentration stage before the Pd-membrane unit is mandatory because of the very low tritium concentration in the He which leaves the breeding blanket of the fusion reactor. The most suitable operating conditions could be reached by: (i) increasing the hydrogen partial pressure in the lumen side and (ii) decreasing the shell pressure. The preliminary design of a membrane unit has been carried out for the case of the DEMO fusion reactor: the optimized membrane module consists of an array of 182 Pd-Ag tubes of 500 mm length, 10 mm diameter, and 0.100 mm wall thickness (total active area of 2.85 m 2 ).

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Section: Tritium Extraction System For a Hcpb Breeding Blanketmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

et al. 2016

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“…[31,32,33] In the PMR, water and carbon monoxide (CO) are catalytically reacted to form carbon dioxide (CO 2 ) and hydrogen at elevated temperatures and pressures (up to 425 o C and 2-3 atmospheres, respectively). The hydrogen is recovered by diffusion through a palladium (Pd) membrane (driven by the partial pressure difference between the process pressure on one side and vacuum on the other side), which is selectively permeable to hydrogen.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of Technologies to Complement/Replace Mass Spectrometers in the Tritium Facilities

Tovo¹,

Lascola²,

Spencer³

et al. 2005

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EXECUTIVE SUMMARYThe problem of the aging mass spectrometers coupled with lack of vendor support and no viable commercially available replacement presents risks for process control and monitoring in the Tritium Facilities. Therefore, several technologies were evaluated to maintain and, if possible, to enhance the current analytical capabilities provided by the existing mass spectrometers. These technologies included potential replacement/complement mass spectrometers as well as on-line sensors. Based on the results of this evaluation, the Savannah River National Laboratory (SRNL) makes the following recommendations.• Work should begin on implementation of the Quantra Fourier Transform-Ion CyclotronResonance (FT-ICR) as a complement to the existing mass spectrometers or as an on-line process analyzer. In its current configuration, the instrument can measure masses 12 or greater, with a resolution of 30,000 at mass 28, and 100 part per million detection limit using ion ejection of major ions. Thus, the 16-24 mass region that is not so easily separated by the existing Tritium Facility mass spectrometers could be resolved and measured using the FT-ICR. For the FT-ICR (Quantra) to be of even more benefit to the Tritium Facilities, it should be reengineered to provide analysis of masses 2-1000 in a single scan as well as other hardware and software improvements identified during our evaluation (i.e. long term stability, quantitative analysis of mixtures, etc.). In collaboration, SRS, LANL, and Y12 have secured funding for this project and the re-engineering effort will begin in FY06. Once the re-engineering effort is complete, funding will be required for performance testing and implementation in a tritiated environment as well as validation with the design agency.• The bench top magnetic sector mass spectrometer (GCMATE) technology closely matches that of the existing mass spectrometers in the Tritium Facilities. The initial work with the GCMATE indicates that its resolution and sensitivity meet the requirements of a replacement mass spectrometer for the Tritium Facilities. Although this instrument appears to be the most promising as a replacement for the existing mass spectrometers, delayed funding in FY05 precluded a complete evaluation. Therefore, evaluation of this instrument should continue in FY06.• Fiber optic Raman Spectroscopy has been demonstrated as a useful on-line technology for measurement of hydrogen isotopes at a concentration of greater than 1%. The method should be demonstrated on a process containing tritium. Upon successful demonstration in a tritium process, the method should then be implemented on the Hydrogen-Tritium Thermal Cycling Adsorption Process (HT-TCAP) and other processes that would require a detection limit of 1% or greater. Research and development to improve the detection limit of the fiber optic Raman method should continue as this would allow on-line analysis of other process points (i.e. HT-TCAP product and raffinate, Tritium Process Stripper, etc.).• The on-line vapochromic sens...

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“…Intensive study has focused on processes using Pd-Ag membrane permeators for application in plasma exhaust processing and recycling, especially for use in the International Thermonuclear Experimental Reactor (ITER). [2][3][4][5][6] However, application of these permeators to low tritium-concentrations and to water vapor processing seems difficult. Instead of a Pd membrane, a blanket tritium recovery system with an electrochemical hydrogen pump using a proton-conducting membrane has been proposed.…”

Section: Introductionmentioning

confidence: 99%

Application of Proton-conducting Ceramics and Polymer Permeable Membranes for Gaseous Tritium Recovery

Asakura

Sugiyama

Kawano

et al. 2004

J. Nucl. Sci. Technol.

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In order to carry out deuterium plasma experiments on the Large Helical Device (LHD), the National Institute for Fusion Science (NIFS) is planning to install a system for the recovery of tritium from exhaust gas and effluent liquid. As well as adopting proven conventional tritium recovery systems, NIFS is planning to apply the latest technologies such as proton-conducting ceramics and membrane-type dehumidifiers in an overall strategy to ensure minimal risk in the tritium recovery process. Application of these new technologies to the tritium recovery system for the LHD deuterium plasma experiment is evaluated quantitatively using recent experimental data.

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Tritium recovery from tritiated water with a two-stage palladium membrane reactor

Cited by 26 publications

References 4 publications

Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

Design of a Multi-Tube Pd-Membrane Module for Tritium Recovery from He in DEMO

Evaluation of Technologies to Complement/Replace Mass Spectrometers in the Tritium Facilities

Application of Proton-conducting Ceramics and Polymer Permeable Membranes for Gaseous Tritium Recovery

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