Nuclear Fusion

Nuclear Fusion is the acknowledged world-leading journal specializing in fusion. The journal covers all aspects of research, theoretical and practical, relevant to controlled thermonuclear fusion.

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3.2

最新論文

Current ramp-up studies for NSTX-U in support of the development of non-inductive current ramp-up scenarios in STs
The impact of kinetic and global effects on ideal ballooning 2nd stable pedestals of conventional and low aspect-ratio tokamaks
Boundary turbulence simulations of the optimized HSX stellarator and comparison with experiments
Enabling integrated AI control on DIII-D: a control system design with state-of-the-art experiments
Ex situ investigation of boron, hydrogen, and oxygen distributions on W7-X divertor surfaces using picosecond-LIBS under vacuum

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Nuclear Fusion

最新論文

Nuclear Fusion

最新論文

Temperature dependence of pinches in tokamaks

Evaluation of disposal, recycling and clearance scenarios for managing ARIES radwaste after plant decommissioning

Clearance considerations for slightly-irradiated components of fusion power plants

A zero-waste option: recycling and clearance of activated vanadium alloys

Revision of the inventory and recycling scenario of active material in near-term PPCS models

New technique for non-destructive measurements of tritium in future fusion reactors

Tritium inventories and tritium safety design principles for the fuel cycle of ITER

Collection and analysis of component failure data from jet systems: neutral beam injectors and power supply

Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module

Safety assessment of Chinese ITER TBM design with helium-cooled solid breeder concept

Review of accidental safety studies for the European HCPB test blanket system

Recent accomplishments and future directions in the US Fusion Safety and Environmental Program

Status of IFE safety and environmental activities in the US

Main safety issues at the transition from ITER to fusion power plants

Safety aspects of fusion power plants

Chapter 9: ITER contributions for Demo plasma development

Chapter 8: Plasma operation and control

Chapter 7: Diagnostics

Chapter 6: Steady state operation

Chapter 4: Power and particle control

Chapter 3: MHD stability, operational limits and disruptions

Chapter 2: Plasma confinement and transport

Chapter 1: Overview and summary

Progress in the ITER Physics Basis

Study of the β dependence of confinement and heat transport in ASDEX Upgrade

Discrepancy between modelled and measured radial electric fields in the scrape-off layer of divertor tokamaks: a challenge for 2D fluid codes?

Modelling of DEMO core plasma consistent with SOL/divertor simulations for long-pulse scenarios with impurity seeding

Progress in the development of heating systems towards long pulse operation for KSTAR

Technology development for the construction of the ITER superconducting magnet system

Impact of nonlocal electron heat transport on the high temperature plasmas of LHD