Conceptual Design of a Compact Helical Fusion Reactor FFHR-c1 for the Early Demonstration of a Year-Long Electric Power Generation

Nuclear Fusion - United Kingdom
doi 10.1088/1741-4326/ab15c3
Full Text
Abstract

Available in full text

Date
Authors
Publisher

IOP Publishing

Related search

Conceptual Design of an Indirect-Cooled Superconducting Magnet for the LHD-type Fusion Reactor FFHR

Fusion Engineering and Design
Materials ScienceMechanical EngineeringCivilNuclear EnergyStructural EngineeringEngineering
2007English

Conceptual Design Study of a Scyllac Fusion Test Reactor

1975English

Conceptual Design and Development of an Indirect-Cooled Superconducting Helical Coil in the FFHR

Plasma and Fusion Research
Condensed Matter Physics
2010English

ORNL Fusion Power Demonstration Study: Arguments for a Vacuum Building in Which to Enclose a Fusion Reactor

1976English

Minimization of the External Heating Power by Long Fusion Power Rise-Up Time for Self-Ignition Access in the Helical Reactor FFHR2m

Nuclear Fusion
High Energy PhysicsNuclearCondensed Matter Physics
2007English

Assessment of Plasma Performance in a Magnetic Configuration With Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1

Plasma and Fusion Research
Condensed Matter Physics
2012English

Tritium Instrumentation for a Fusion Reactor Power Plant

1976English

Tokamak Experimental Power Reactor Conceptual Design. Volume I

1976English

Conceptual Design of a Laser Fusion Power Plant. Part I. An Integrated Facility

1981English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy