Tritium Transport in WCLL Outboard Breeding Blanket of EU-DEMO Reactor Under Pulsed Plasma Operation-Reference-Cited by-同舟云学术

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Tritium Transport in WCLL Outboard Breeding Blanket of EU-DEMO Reactor Under Pulsed Plasma Operation

Published:2023-03-20 Issue:8 Volume:79 Page:1197-1207
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Candido Luigi¹²^ORCID,Alberghi Ciro¹³^ORCID,Arena Pietro³^ORCID,Moro Fabio⁴^ORCID,Noce Simone⁵^ORCID,Utili Marco³^ORCID,Zucchetti Massimo¹⁶^ORCID

Affiliation:

1. ESSENTIAL Group, Politecnico di Torino, Corso Duca degli Abruzzi, 24, 10129, Torino, Italy

2. Fusion for Energy at ITER Organization, Route de Vinon-sur-Verdon, 13115, Saint-Paul-lez-Durance, France

3. ENEA-FSN, C. R. Brasimone, Località Brasimone, Camugnano, 40032, Bologna Italy

4. ENEA-FSN, C. R. Frascati, Via E. Fermi 45, Frascati, 00044, Rome, Italy

5. University of Rome Tor Vergata, Industrial Engineering Department, Via del Politecnico, 1, 00133, Rome, Italy

6. MIT, Massachusetts Institute of Technology, Cambridge, Massachusetts

Funder

EUROfusion

Publisher

Informa UK Limited

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Civil and Structural Engineering

Link

https://www.tandfonline.com/doi/pdf/10.1080/15361055.2023.2173711

Reference16 articles.

1. Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems

2. Recent progress in developing a feasible and integrated conceptual design of the WCLL BB in EUROfusion project

3. The DEMO Water-Cooled Lead–Lithium Breeding Blanket: Design Status at the End of the Pre-Conceptual Design Phase

4. The issue of Tritium in DEMO coolant and mitigation strategies

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

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