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Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format Example of Nuclear Materials and Energy format
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open access Open Access

Nuclear Materials and Energy — Template for authors

Publisher: Elsevier
Categories Rank Trend in last 3 yrs
Nuclear Energy and Engineering #10 of 66 up up by 19 ranks
Materials Science (miscellaneous) #20 of 98 up up by 12 ranks
Nuclear and High Energy Physics #19 of 75 up up by 27 ranks
journal-quality-icon Journal quality:
High
calendar-icon Last 4 years overview: 702 Published Papers | 3081 Citations
indexed-in-icon Indexed in: Scopus
last-updated-icon Last updated: 26/06/2020
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Related Journals

open access Open Access

IEEE

Quality:  
High
CiteRatio: 3.5
SJR: 0.537
SNIP: 1.338
open access Open Access

Elsevier

Quality:  
High
CiteRatio: 5.0
SJR: 1.123
SNIP: 1.381
open access Open Access

Elsevier

Quality:  
High
CiteRatio: 3.5
SJR: 1.147
SNIP: 1.566
open access Open Access

Taylor and Francis

Quality:  
Good
CiteRatio: 2.8
SJR: 0.668
SNIP: 1.21

Journal Performance & Insights

CiteRatio

SCImago Journal Rank (SJR)

Source Normalized Impact per Paper (SNIP)

A measure of average citations received per peer-reviewed paper published in the journal.

Measures weighted citations received by the journal. Citation weighting depends on the categories and prestige of the citing journal.

Measures actual citations received relative to citations expected for the journal's category.

4.4

19% from 2019

CiteRatio for Nuclear Materials and Energy from 2016 - 2020
Year Value
2020 4.4
2019 3.7
2018 2.5
2017 1.2
2016 0.3
graph view Graph view
table view Table view

1.324

35% from 2019

SJR for Nuclear Materials and Energy from 2016 - 2020
Year Value
2020 1.324
2019 0.983
2018 1.006
2017 0.778
2016 0.5
graph view Graph view
table view Table view

0.995

17% from 2019

SNIP for Nuclear Materials and Energy from 2016 - 2020
Year Value
2020 0.995
2019 1.198
2018 1.037
2017 1.379
2016 0.972
graph view Graph view
table view Table view

insights Insights

  • CiteRatio of this journal has increased by 19% in last years.
  • This journal’s CiteRatio is in the top 10 percentile category.

insights Insights

  • SJR of this journal has increased by 35% in last years.
  • This journal’s SJR is in the top 10 percentile category.

insights Insights

  • SNIP of this journal has decreased by 17% in last years.
  • This journal’s SNIP is in the top 10 percentile category.

Nuclear Materials and Energy

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Elsevier

Nuclear Materials and Energy

Nuclear Materials and Energy publishes concise original research articles. Longer critical review papers and topical reviews are also welcome. The Journal can stimulate research and interest by soliciting invited reviews. The manuscripts must contain new experimental results a...... Read More

Materials Science

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Last updated on
25 Jun 2020
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ISSN
2352-1791
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Acceptance Rate
Not provided
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Frequency
Not provided
i
Open Access
Yes
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Plagiarism Check
Available via Turnitin
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Endnote Style
Download Available
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Bibliography Name
elsarticle-num
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Citation Type
Numbered
[25]
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Bibliography Example
G. E. Blonder, M. Tinkham, T. M. Klapwijk, Transition from metallic to tunneling regimes in superconducting microconstrictions: Excess current, charge imbalance, and supercurrent conversion, Phys. Rev. B 25 (7) (1982) 4515–4532. URL 10.1103/PhysRevB.25.4515

Top papers written in this journal

open accessOpen access Journal Article DOI: 10.1016/J.NME.2019.100696
Physics basis for the first ITER tungsten divertor

Abstract:

On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fi... On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor lifetime constraint. The principal focus is on the main design driver, steady state power fluxes in the DT phases, obtained from simulations using the 2-D SOLPS-4.3 and SOLPS-ITER plasma boundary codes, assuming the use of the low Z seeding impurities nitrogen (N) and neon (Ne). A new perspective on the simulation database is adopted, concentrating purely on the divertor physics aspects rather than on the core-edge integration, which has been studied extensively in the course of the divertor design evolution and is published elsewhere. Emphasis is placed on factors which may increase the peak steady state loads: divertor target shaping for component misalignment protection, the influence of fluid drifts, and the consequences of narrow scrape-off layer heat flux channels. All tend to push the divertor into an operating space at higher sub-divertor neutral pressure in order to remain at power flux densities acceptable for the target material. However, a revised criterion for the maximum tolerable loads based on avoidance of W recrystallization, sets an upper limit potentially ∼50% higher than the previously accepted value of ∼10 MW m−2, a consequence both of the choice of material and the finalized component design. Although the simulation database is currently restricted to the 2-D toroidally symmetric situation, considerable progress is now also being made using the EMC3-Eirene 3-D code suite for the assessment of power loading in the presence of magnetic perturbations for ELM control. Some new results for low input power corresponding to the early H-mode operation phases are reported, showing that even if realistic plasma screening is taken into account, significant asymmetric divertor heat fluxes may arise far from the unperturbed strike point. The issue of tolerable limits for transient heat pulses is an open and key question. A new scaling for ELM power deposition has shown that whilst there may be more latitude for operation at higher current without ELM control, the ultimate limit is likely to be set more by material fatigue under large numbers of sub-threshold melting events. read more read less

Topics:

Divertor (65%)65% related to the paper
312 Citations
open accessOpen access Journal Article DOI: 10.1016/J.NME.2016.07.003
Use of Tungsten Material for the ITER Divertor
ITER1

Abstract:

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 hea... 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 tungsten monoblock components. Not systematically but frequently macro-cracks appeared at the middle of monoblocks after 20 MW/m2 loading. The initiation of such macro-cracks was considered to be due to cyclic exposure to high temperature, ∼2000 °C, where creep, recrystallization and low cycle fatigue were concerned. To understand correlation between the macro-crack appearance and mechanical properties and possible update of acceptance criteria in the material specification, an activity to characterize the tungsten monoblocks was launched. read more read less

Topics:

Divertor (55%)55% related to the paper
215 Citations
open accessOpen access Journal Article DOI: 10.1016/J.NME.2016.02.005
European DEMO divertor target: Operational requirements and material-design interface

Abstract:

Recently, an integrated program of conceptual design activities for the European DEMO reactor was launched in the framework of the EUROfusion Consortium, where reliable power handling capability was identified as one of the most critical scientific as well as technological challenges for a DEMO reactor. The divertor is the ke... Recently, an integrated program of conceptual design activities for the European DEMO reactor was launched in the framework of the EUROfusion Consortium, where reliable power handling capability was identified as one of the most critical scientific as well as technological challenges for a DEMO reactor. The divertor is the key in-vessel plasma-facing component being in charge of power exhaust and removal of impurity particles. The DEMO divertor target will have to withstand extreme thermal loads where the local peak heat flux is expected to reach up to 20 MW/m2 during slow transient events in DEMO. To assure sufficient heat removal capability of the divertor target against normal and transient operational scenarios under expected cumulative neutron dose of up to 13 dpa is one of the fundamental engineering challenges imposed on target design. To develop the design of the DEMO divertor and related technologies, an R&D work package ‘Divertor’ has been set up in this consortium. The subproject ‘Target Development’ is devoted to the development of the conceptual design and the core technologies of the plasma-facing target. Devising and implementing novel structural heat sink materials (e.g. W/Cu composites) to advanced target design concepts is one of the major objectives of this subproject. In this paper, the underlying design requirements imposed by the envisaged power exhaust goal and the prominent material-design interface issues are discussed. In addition, the candidate design concepts being currently considered are presented together with the related material issues. Finally, the first results achieved so far are presented. read more read less

Topics:

Conceptual design (54%)54% related to the paper, Divertor (52%)52% related to the paper
120 Citations
open accessOpen access Journal Article DOI: 10.1016/J.NME.2017.03.005
Physics conclusions in support of ITER W divertor monoblock shaping

Abstract:

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 ... 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 heat loads, magnetic shadowing of these edges is required if quasi-steady state melting is to be avoided under certain conditions during burning plasma operation and transiently during edge localized mode (ELM) or disruption induced power loading. An experiment on JET in 2013 designed to investigate the consequences of transient W edge melting on ITER, found significant deficits in the edge power loads expected on the basis of simple geometric arguments, throwing doubt on the understanding of edge loading at glancing field line angles. As a result, a coordinated multi-experiment and simulation effort was initiated via the International Tokamak Physics Activity (ITPA) and through ITER contracts, aimed at improving the physics basis supporting a MB shaping decision from the point of view both of edge power loading and melt dynamics. This paper reports on the outcome of this activity, concluding first that the geometrical approximation for leading edge power loading on radially misaligned poloidal leading edges is indeed valid. On this basis, the behaviour of shaped and unshaped monoblock surfaces under stationary and transient loads, with and without melting, is compared in order to examine the consequences of melting, or power overload in context of the benefit, or not, of shaping. The paper concludes that MB top surface shaping is recommended to shadow poloidal gap edges in the high heat flux areas of the ITER divertor targets. read more read less

Topics:

Divertor (57%)57% related to the paper, Leading edge (55%)55% related to the paper, Edge-localized mode (53%)53% related to the paper, Tokamak (51%)51% related to the paper
View PDF
120 Citations
open accessOpen access Journal Article DOI: 10.1016/J.NME.2017.04.014
ELM divertor peak energy fluence scaling to ITER with data from JET, MAST and ASDEX upgrade
T. Eich1, B. Sieglin1, A.J. Thornton, M. Faitsch1, A. Kirk, A. Herrmann1, W. Suttrop1

Abstract:

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 an ... 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 an ... read more read less

Topics:

ASDEX Upgrade (62%)62% related to the paper, Divertor (54%)54% related to the paper
View PDF
100 Citations
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Nuclear Materials and Energy format uses elsarticle-num citation style.

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Frequently asked questions

1. Can I write Nuclear Materials and Energy in LaTeX?

Absolutely not! Our tool has been designed to help you focus on writing. You can write your entire paper as per the Nuclear Materials and Energy guidelines and auto format it.

2. Do you follow the Nuclear Materials and Energy guidelines?

Yes, the template is compliant with the Nuclear Materials and Energy guidelines. Our experts at SciSpace ensure that. If there are any changes to the journal's guidelines, we'll change our algorithm accordingly.

3. Can I cite my article in multiple styles in Nuclear Materials and Energy?

Of course! We support all the top citation styles, such as APA style, MLA style, Vancouver style, Harvard style, and Chicago style. For example, when you write your paper and hit autoformat, our system will automatically update your article as per the Nuclear Materials and Energy citation style.

4. Can I use the Nuclear Materials and Energy templates for free?

Sign up for our free trial, and you'll be able to use all our features for seven days. You'll see how helpful they are and how inexpensive they are compared to other options, Especially for Nuclear Materials and Energy.

5. Can I use a manuscript in Nuclear Materials and Energy that I have written in MS Word?

Yes. You can choose the right template, copy-paste the contents from the word document, and click on auto-format. Once you're done, you'll have a publish-ready paper Nuclear Materials and Energy that you can download at the end.

6. How long does it usually take you to format my papers in Nuclear Materials and Energy?

It only takes a matter of seconds to edit your manuscript. Besides that, our intuitive editor saves you from writing and formatting it in Nuclear Materials and Energy.

7. Where can I find the template for the Nuclear Materials and Energy?

It is possible to find the Word template for any journal on Google. However, why use a template when you can write your entire manuscript on SciSpace , auto format it as per Nuclear Materials and Energy's guidelines and download the same in Word, PDF and LaTeX formats? Give us a try!.

8. Can I reformat my paper to fit the Nuclear Materials and Energy's guidelines?

Of course! You can do this using our intuitive editor. It's very easy. If you need help, our support team is always ready to assist you.

9. Nuclear Materials and Energy an online tool or is there a desktop version?

SciSpace's Nuclear Materials and Energy is currently available as an online tool. We're developing a desktop version, too. You can request (or upvote) any features that you think would be helpful for you and other researchers in the "feature request" section of your account once you've signed up with us.

10. I cannot find my template in your gallery. Can you create it for me like Nuclear Materials and Energy?

Sure. You can request any template and we'll have it setup within a few days. You can find the request box in Journal Gallery on the right side bar under the heading, "Couldn't find the format you were looking for like Nuclear Materials and Energy?”

11. What is the output that I would get after using Nuclear Materials and Energy?

After writing your paper autoformatting in Nuclear Materials and Energy, you can download it in multiple formats, viz., PDF, Docx, and LaTeX.

12. Is Nuclear Materials and Energy's impact factor high enough that I should try publishing my article there?

To be honest, the answer is no. The impact factor is one of the many elements that determine the quality of a journal. Few of these factors include review board, rejection rates, frequency of inclusion in indexes, and Eigenfactor. You need to assess all these factors before you make your final call.

13. What is Sherpa RoMEO Archiving Policy for Nuclear Materials and Energy?

SHERPA/RoMEO Database

We extracted this data from Sherpa Romeo to help researchers understand the access level of this journal in accordance with the Sherpa Romeo Archiving Policy for Nuclear Materials and Energy. The table below indicates the level of access a journal has as per Sherpa Romeo's archiving policy.

RoMEO Colour Archiving policy
Green Can archive pre-print and post-print or publisher's version/PDF
Blue Can archive post-print (ie final draft post-refereeing) or publisher's version/PDF
Yellow Can archive pre-print (ie pre-refereeing)
White Archiving not formally supported
FYI:
  1. Pre-prints as being the version of the paper before peer review and
  2. Post-prints as being the version of the paper after peer-review, with revisions having been made.

14. What are the most common citation types In Nuclear Materials and Energy?

The 5 most common citation types in order of usage for Nuclear Materials and Energy are:.

S. No. Citation Style Type
1. Author Year
2. Numbered
3. Numbered (Superscripted)
4. Author Year (Cited Pages)
5. Footnote

15. How do I submit my article to the Nuclear Materials and Energy?

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16. Can I download Nuclear Materials and Energy in Endnote format?

Yes, SciSpace provides this functionality. After signing up, you would need to import your existing references from Word or Bib file to SciSpace. Then SciSpace would allow you to download your references in Nuclear Materials and Energy Endnote style according to Elsevier guidelines.

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