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Nuclear Materials and Energy

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DOIs for this ISSN

Showing the top 5 of 2071 DOIs, ordered by correction priority.

# Title Missing Priority Citations
1 Physics basis for the first ITER tungsten divertor (10.1016/j.nme.2019.100696)
Abstract ORCID
135.80 519
2 ELM divertor peak energy fluence scaling to ITER with data f… (10.1016/j.nme.2017.04.014)
Abstract ORCID
112.88 180
3 Physics conclusions in support of ITER W divertor monoblock… (10.1016/j.nme.2017.03.005)
Abstract ORCID
112.64 178
4 Hydrogen permeation barriers: Basic requirements, materials… (10.1016/j.nme.2019.04.001)
Abstract ORCID
112.03 173
5 Analytical expressions for thermophysical properties of soli… (10.1016/j.nme.2017.08.002)
Abstract ORCID
110.87 164
6 European DEMO divertor target: Operational requirements and… (10.1016/j.nme.2016.02.005)
Abstract ORCID
109.38 153
7 European divertor target concepts for DEMO: Design rationale… (10.1016/j.nme.2018.05.012)
Abstract ORCID
107.31 139
8 Power exhaust by SOL and pedestal radiation at ASDEX Upgrade… (10.1016/j.nme.2016.12.029)
Abstract ORCID
106.19 132
9 Copper matrix composites as heat sink materials for water-co… (10.1016/j.nme.2015.10.001)
Abstract ORCID
99.78 98
10 The high field side high density region in SOLPS-modeling of… (10.1016/j.nme.2017.01.010)
Abstract ORCID
99.34 96
11 Microstructure and mechanical properties of mechanically all… (10.1016/j.nme.2018.05.019)
Abstract ORCID
99.11 95
12 Efficiency of thermal outgassing for tritium retention measu… (10.1016/j.nme.2016.10.016)
Abstract ORCID
95.42 80
13 Mechanical and microstructural investigations of tungsten an… (10.1016/j.nme.2015.04.002)
Abstract ORCID
93.46 73
14 The influence of annealing on yttrium oxide thin film deposi… (10.1016/j.nme.2016.12.031)
Abstract ORCID
92.87 71
15 Manufacturing and testing of self-passivating tungsten alloy… (10.1016/j.nme.2016.06.002)
Abstract ORCID
91.94 68
16 Deuterium retention in MeV self-implanted tungsten: Influenc… (10.1016/j.nme.2017.02.003)
Abstract ORCID
91.63 67
17 Recent progress on the R&D of W-ZrC alloys for plasma fa… (10.1016/j.nme.2018.07.002)
Abstract ORCID
91.30 66
18 Self-castellation of tungsten monoblock under high heat flux… (10.1016/j.nme.2016.10.025)
Abstract ORCID
88.54 58
19 Pebble fabrication of super advanced tritium breeders using… (10.1016/j.nme.2016.05.004)
Abstract ORCID
86.62 53
20 Suppression of tungsten accumulation during ELMy H-mode by l… (10.1016/j.nme.2017.01.009)
Abstract ORCID
86.62 53
21 Influence of the presence of deuterium on displacement damag… (10.1016/j.nme.2018.10.005)
Abstract ORCID
86.21 52
22 Recent advances towards a lithium vapor box divertor (10.1016/j.nme.2017.03.020)
Abstract ORCID
85.80 51
23 A growth/annealing equilibrium model for helium-induced nano… (10.1016/j.nme.2019.01.034)
Abstract ORCID
84.95 49
24 Effect of Cr/Al contents on the 475 º C age-hardening in oxi… (10.1016/j.nme.2016.05.015)
Abstract ORCID
84.06 47
25 Spectroscopic investigations of divertor detachment in TCV (10.1016/j.nme.2017.01.004)
Abstract ORCID
84.06 47
26 Studies of dust from JET with the ITER-Like Wall: Compositio… (10.1016/j.nme.2016.11.027)
Abstract ORCID
83.60 46
27 IFMIF, the European–Japanese efforts under the Broader Appro… (10.1016/j.nme.2016.04.012)
Abstract ORCID
83.14 45
28 Power handling of a liquid-metal based CPS structure under h… (10.1016/j.nme.2017.01.017)
Abstract ORCID
83.14 45
29 Impact of wall materials and seeding gases on the pedestal a… (10.1016/j.nme.2017.01.002)
Abstract ORCID
82.17 43
30 Determination of deuterium depth profiles in fusion-relevant… (10.1016/j.nme.2017.05.013)
Abstract ORCID
82.17 43
31 Retention in tungsten resulting from extremely high fluence… (10.1016/j.nme.2016.04.008)
Abstract ORCID
81.67 42
32 Deuterium retention in W and W-Re alloy irradiated with high… (10.1016/j.nme.2016.06.016)
Abstract ORCID
81.67 42
33 Role of molecular effects in divertor plasma recombination (10.1016/j.nme.2016.12.030)
Abstract ORCID
81.67 42
34 ColRadPy: A Python collisional radiative solver (10.1016/j.nme.2019.01.013)
Abstract ORCID
81.67 42
35 Implications of PMI and wall material choice on fusion react… (10.1016/j.nme.2018.12.006)
Abstract ORCID
81.16 41
36 ODS-materials for high temperature applications in advanced… (10.1016/j.nme.2016.08.017)
Abstract ORCID
80.64 40
37 Energy balance in plasma detachment (10.1016/j.nme.2017.03.019)
Abstract ORCID
80.10 39
38 Study on irradiation effects of refractory bcc high-entropy… (10.1016/j.nme.2022.101158)
Abstract ORCID
79.55 38
39 Crystallization and deuterium permeation behaviors of yttriu… (10.1016/j.nme.2016.06.009)
Abstract ORCID
78.99 37
40 Ion orbit modelling of ELM heat loads on ITER divertor verti… (10.1016/j.nme.2016.10.005)
Abstract ORCID
78.99 37
41 Tungsten melting and erosion under plasma heat load in tokam… (10.1016/j.nme.2016.11.029)
Abstract ORCID
78.99 37
42 Irradiation effects of hydrogen and helium plasma on differe… (10.1016/j.nme.2017.01.018)
Abstract ORCID
78.99 37
43 Structural impact of creep in tungsten monoblock divertor ta… (10.1016/j.nme.2017.12.001)
Abstract ORCID
78.99 37
44 Molecular activated recombination in divertor simulation pla… (10.1016/j.nme.2017.05.001)
Abstract ORCID
78.41 36
45 Nano-indentation of ion-irradiated nuclear structural materi… (10.1016/j.nme.2019.100721)
Abstract ORCID
78.41 36
46 Impact of plasma-wall interaction and exhaust on the EU-DEMO… (10.1016/j.nme.2020.100897)
Abstract ORCID
78.41 36
47 Proposal of an alternative upper divertor in ASDEX Upgrade s… (10.1016/j.nme.2016.12.035)
Abstract ORCID
77.82 35
48 ERO modelling of tungsten erosion in the linear plasma devic… (10.1016/j.nme.2017.03.014)
Abstract ORCID
77.82 35
49 Deuterium retention in tungsten simultaneously damaged by hi… (10.1016/j.nme.2016.11.010)
Abstract ORCID
77.20 34
50 The effect of divertor closure on detachment onset in DIII-D (10.1016/j.nme.2019.01.017)
Abstract ORCID
77.20 34