Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios | Citedby Results | ASME J. of Nuclear Rad Sci. | ASME Digital Collection

Skip to Main Content

Skip Nav Destination

Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios

ASME J of Nuclear Rad Sci. Jul 2019, 5(3): 030916 (7 pages)

This article has been cited by the following articles in journals that are participating in CrossRef Cited-by Linking.

Thermal-hydraulic optimization of a proposed EU-DEMO hydrogen passive removal system

T. Glingler
G. Caruso
M. D'Onorio

Fusion Engineering and Design. January 2023, 194

Pressure suppression system influence on vacuum vessel thermal-hydraulics and on source term mobilization during a multiple first Wall – Blanket pipe break

Matteo D’Onorio
Gianfranco Caruso

Fusion Engineering and Design. January 2021, 164

A sensitivity analysis of the factors that influence the hazard potential of fusion power plants

M. Lukacs
L.G. Williams

Fusion Engineering and Design. January 2021, 164

Preliminary safety analysis of an in-vessel LOCA for the EU-DEMO WCLL blanket concept

Matteo D’Onorio
Fabio Giannetti
Maria Teresa Porfiri
Gianfranco Caruso

Fusion Engineering and Design. January 2020, 155