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Nuclear Materials and Energy is a peer-reviewed journal published by Elsevier, covering Fusion materials and technologies, Nuclear Materials and Properties, Magnetic confinement fusion research.
| Publisher | Elsevier |
|---|---|
| Reference style | Numbered (Elsevier) Numbered — [1], [2] in the text [1] A. Smith, B. Jones, C. Lee, A representative article title, Nuclear Materials and Energy 12 (2023) 45–58.
Formats any DOI in Nuclear Materials and Energy style. No sign-up. |
| Publishes research in | Fusion materials and technologies Nuclear Materials and Properties Magnetic confinement fusion research Nuclear reactor physics and engineering Metal and Thin Film Mechanics |
| ISSN | 2352-1791 |
| Citation impact (2-yr) | 2.37 |
| h-index | 50 |
| i10-index | 760 |
| Total citations | 23,916 |
| Article processing charge | $1,000 |
| Open access | Yes |
| Top institutions publishing here | Max Planck Institute for Plasma Physics |
| Journal website | www.journals.elsevier.com |
| You get | A submission-ready PDF and the editable LaTeX source — ready to submit. |
Citations each year’s papers have accumulated so far — the most recent years are still building up.
• Reviews the fundamental physics aspects of the first ITER W divertor and defines the required operational lifetime within the Staged Approach. • Uses the ITER divertor SOLPS simulation database to establish the target peak heat flux and neutral pressure burning plasma operating domain. • Assesses consequences of narrow SOL heat flux channels, fluid drifts,…
Since the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R&D for high performance armor-heat sink joint were necessary to be implemented. In the R&D, the availability of the technology was demonstrated by high heat flux test of…
The preferred plasma-facing material in present-day and future magnetic confinement thermonuclear fusion devices is tungsten. This material is mainly chosen because of its high threshold energy for sputtering by hydrogen isotopes as well as its low retention of tritium within the material. From an engineering point of view, however, tungsten is a challenging material to…
The key remaining physics design issue for the ITER tungsten (W) divertor is the question of monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled targets. Engineering tolerance specifications impose a challenging maximum radial step between toroidally adjacent MBs of 0.3 mm. Assuming optical projection of the parallel…
A newly established scaling of the ELM energy fluence using dedicated data sets from JET operation with CFC & ILW plasma facing components (PFCs), ASDEX Upgrade (AUG) operation with both CFC and full-W PFCs and MAST with CFC walls has been generated. The scaling reveals an approximately linear dependence of the peak ELM energy with…
