4.5 Article

Numerical simulation of tritium extraction from liquid PbLi by gas-liquid contactor

Related references

Note: Only part of the references are listed.
Article Nuclear Science & Technology

Conceptual design of the supercritical CO2 cooled lithium lead blanket for CFETR

Lei Chen et al.

Summary: The conceptual design of the supercritical CO2 cooled Lithium-Lead blanket for CFETR aims to achieve high Tritium Breeding Ratio and PbLi outlet temperature, with a preliminary Power Conversion System based on supercritical CO2 recompressing cycle.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Alternatives for upgrading the EU DCLL breeding blanket from MMS to SMS

Ivan Fernandez-Berceruelo et al.

Summary: CIEMAT has been working on developing a low temperature DCLL breeding blanket using the MMS approach to improve competitiveness and reduce electricity costs. In order to achieve this, they are exploring more advanced blanket solutions based on the SMS structure and the use of self-cooled incompressible liquid breeder.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

Conceptual design of a PAV-based tritium extractor for the WCLL breeding blanket of the EU DEMO: Effects of surface-limited vs. diffusion-limited modeling

R. Bonifetto et al.

Summary: The EU DEMO will use a breeding blanket for tritium production and extraction. The conceptual design of the tritium extraction system relies on the tritium dissolved in the liquid PbLi, forced to cross a Nb membrane through permeation against vacuum technology.

FUSION ENGINEERING AND DESIGN (2021)

Article Nuclear Science & Technology

An integrated hydrogen isotopes transport model for the TRIEX-II facility

Luigi Candido et al.

FUSION ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

Tritium technologies and transport modelling: main outcomes from the European TBM Project

I. Ricapito et al.

FUSION ENGINEERING AND DESIGN (2018)

Article Nuclear Science & Technology

Study of hydrogen recovery from Li-Pb using packed tower

Satoshi Fukada et al.

FUSION ENGINEERING AND DESIGN (2018)

Article Nuclear Science & Technology

Design and fabrication of a Permeator Against Vacuum prototype for small scale testing at Lead-Lithium facility

Belit Garcinuno et al.

FUSION ENGINEERING AND DESIGN (2017)

Article Nuclear Science & Technology

Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system

Fumito Okino et al.

FUSION ENGINEERING AND DESIGN (2016)

Article Nuclear Science & Technology

Investigation on efficiency of gas liquid contactor used as tritium extraction unit for HCLL-TBM Pb-16Li loop

M. Utili et al.

FUSION ENGINEERING AND DESIGN (2016)

Article Nuclear Science & Technology

Blanket/first wall challenges and required R&D on the pathway to DEMO

Mohamed Abdou et al.

FUSION ENGINEERING AND DESIGN (2015)

Article Nuclear Science & Technology

TRITIUM EXTRACTION FROM LIQUID Pb-16Li: A CRITICAL REVIEW OF CANDIDATE TECHNOLOGIES FOR ITER AND DEMO APPLICATIONS

I. Ricapito et al.

FUSION SCIENCE AND TECHNOLOGY (2011)

Article Nuclear Science & Technology

Hydrogen extraction from Pb-17Li: results with a 800 mm high packed column

N Alpy et al.

FUSION ENGINEERING AND DESIGN (2000)