Developments on the tritium extraction and recovery system for HCPB

Cristescu, I.; Draghia, Mirela

doi:10.1016/j.fusengdes.2020.111558

Cited by 17 publications

(10 citation statements)

References 2 publications

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“…Looking at the experimental outcomes, considering an inlet composition of 90% H 2 and 10% He, the maximum allowable specific feed flow rate of the mixture is 128.1 mol h −1 m −2 (note that Figure 4 reports only the H 2 -specific feed flow rate on the x-axis ), even though high lumen-side pressure (200 kPa) and high membrane temperature (673 K) are needed. Because of the presence of tritium in the TCS inlet stream (about 1% of mole fraction [ 8 ]), for safety concerns, it could be convenient to operate with reduced pressure. Furthermore, it is worth noticing that direct resistive heating should be avoided for a multi-tube module managing tritium.…”

Section: Resultsmentioning

confidence: 99%

“…Among these, the one coming from the BB represents the major tritium contribution to the OUTL. Referring to the solid blanket concept, the higher throughput expected from the TERS is that coming from the regeneration of CMSB, estimated by Cristescu and Draghia as 10 Nm 3 h −1 consisting in 5–10 mol% of He and the rest Q 2 [ 8 ]. The TCS has the central function of preparing this effluent for the isotope separation, and removing helium from the Q 2 stream.…”

Section: The Tritium Conditioning Systemmentioning

confidence: 99%

“…For this purpose, in comparison with the V series, the analysis was more interested in the low specific feed flow rates. The mixture composition derives from the TERS CMSB regeneration, in accordance with Cristescu and Draghia [ 8 ]. An overall number of 80 tests were performed, each one repeated twice for the repeatability assessment.…”

Section: The Experimental Campaignmentioning

confidence: 99%

“…The tritium produced in the pebbles is released by purging with a helium stream doped with protium, from which it has to be opportunely recovered and purified in a closed loop, namely the Tritium Extraction and Recovery System (TERS). Currently, the reference process for the TERS relies on the sequential use of Reactive Molecular Sieve Beds (RMSB) and Cryogenic Molecular Sieve Beds (CMSB) [ 8 ]. A schematic view of the TERS operating principle is given in the diagram of Figure 1 .…”

Section: Introductionmentioning

confidence: 99%

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Experimental and Numerical Analysis of a Pd–Ag Membrane Unit for Hydrogen Isotope Recovery in a Solid Blanket

Narcisi,

Tamborrini,

Farina

et al. 2023

Membranes

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The interest of the fusion community in Pd–Ag membranes has grown in the last decades due to the high value of hydrogen permeability and the possibility of continuous operation, making it a promising technology when a gaseous stream of hydrogen isotopes must be recovered and separated from other impurities. This is the case of the Tritium Conditioning System (TCS) of the European fusion power plant demonstrator, called DEMO. This paper presents an experimental and numerical activity aimed at (i) assessing the Pd–Ag permeator performance under TCS-relevant conditions, (ii) validating a numerical tool for scale-up purposes, and (iii) carrying out a preliminary design of a TCS based on Pd–Ag membranes. Experiments were performed by feeding the membrane with a He–H2 gas mixture in a specific feed flow rate ranging from 85.4 to 427.2 mol h−1 m−2. A satisfactory agreement between experiments and simulations was obtained over a wide range of compositions, showing a root mean squared relative error of 2.3%. The experiments also recognized the Pd–Ag permeator as a promising technology for the DEMO TCS under the identified conditions. The scale-up procedure ended with a preliminary sizing of the system, relying on multi-tube permeators with an overall number ranging between 150 and 80 membranes in lengths of 500 and 1000 mm each.

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Section: Resultsmentioning

confidence: 99%

Section: The Tritium Conditioning Systemmentioning

confidence: 99%

Section: The Experimental Campaignmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Experimental and Numerical Analysis of a Pd–Ag Membrane Unit for Hydrogen Isotope Recovery in a Solid Blanket

Narcisi,

Tamborrini,

Farina

et al. 2023

Membranes

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“…3.73 m³/s at a temperature of 450 °C and pressure of 0.2 MPa). This flow rate has been used for the design of the HCPB TER [25]. The resulting plant purge gas mass flow rate is about 0.5 kg/s, which results in a reasonable TER system size, considered to be ready for its industrialization [25].…”

Section: Purge Gas Choice Parameters and Flow Schemementioning

confidence: 99%

The European DEMO HCPB Breeding Blanket: Design Status at the End of Pre-Concept Design Phase

Zhou¹,

Hernández²,

Pereslavtsev³

et al. 2023

Preprint

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Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO programme to optimize the Helium Cooled Pebble Bed (HCPB) breeding blanket. A Gate Review was conducted for the entire European DEMO programme at the conclusion of the PCD phase. This article presents a summary of the design evolution and the rationale behind the HCPB breeding blanket concept for the European DEMO. The main performance metrics, including nuclear, thermal hydraulics, thermal mechanical, and tritium permeation behaviors, are reported. These figures demonstrate that the HCPB breeding blanket is a highly effective tritium-breeding and robust driver blanket concept for the European DEMO. In addition, three alternative concepts of interest were explored. Furthermore, this article outlines the upcoming design and R&D activities for the HCPB breeding blanket during the Concept Design phase (2021-2027).

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Magnetic Confinement Fusion—Reactor Blanket Technologies

Boccaccini¹,

Day²

2021

Encyclopedia of Nuclear Energy

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Developments on the tritium extraction and recovery system for HCPB

Cited by 17 publications

References 2 publications

Experimental and Numerical Analysis of a Pd–Ag Membrane Unit for Hydrogen Isotope Recovery in a Solid Blanket

Experimental and Numerical Analysis of a Pd–Ag Membrane Unit for Hydrogen Isotope Recovery in a Solid Blanket

The European DEMO HCPB Breeding Blanket: Design Status at the End of Pre-Concept Design Phase

Magnetic Confinement Fusion—Reactor Blanket Technologies

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