OOIR: Observatory of International Research

Papers

(The H4-Index of Fusion Engineering and Design is 26. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2020-05-01 to 2024-05-01.)

Article	Citations
Overview of recent ITER TBM Program activities	63
Consolidated design of the HCPB Breeding Blanket for the pre-Conceptual Design Phase of the EU DEMO and harmonization with the ITER HCPB TBM program	58
Divertor of the European DEMO: Engineering and technologies for power exhaust	53
DTT - Divertor Tokamak Test facility: A testbed for DEMO	52
Status of maturation of critical technologies and systems design: Breeding blanket	46
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems	46
On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress	44
DEMO physics challenges beyond ITER	42
The DEMO magnet system – Status and future challenges	42
Engineering design of the CFETR machine	37
Design and preliminary analyses of the new Water Cooled Lithium Lead TBM for ITER	36
Required, achievable and target TBR for the European DEMO	34
Preliminary design of the COMPASS upgrade tokamak	33
On the standards and practices for miniaturized tensile test – A review	33
LIBS measurements inside the FTU vessel mock-up by using a robotic arm	30
Eurofusion-DEMO Divertor - Cassette Design and Integration	29
An overview of the numerical methods for tokamak plasma equilibrium computation implemented in the NICE code	29
Key design integration issues addressed in the EU DEMO pre-concept design phase	28
Manufacturing and high heat flux testing of flat-type W/Cu/CuCrZr mock-up by HIP assisted brazing process	28
Development of load specifications for the design of the breeding blanket system	28
Tokamak cooling systems and power conversion system options	28
Pre-conceptual design of EU DEMO balance of plant systems: Objectives and challenges	28
Deployment of multiple shattered pellet injection systems in KSTAR	27
Conceptual design of HTS magnets for fusion nuclear science facility	27
Role of heat-treatment and filler on structure-property relationship of dissimilar welded joint of P22 and F69 steel	27

DEMO – The main achievements of the Pre – Concept phase of the safety and environmental work package and the development of the GSSR	27
Plasma-facing components damage and its effects on plasma performance in EAST tokamak	26
Development of anti-permeation and corrosion barrier coatings for the WCLL breeding blanket of the European DEMO	26
Current status and future perspectives of EU ceramic breeder development	26
Maturation of critical technologies for the DEMO balance of plant systems	26