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exaly
›
Journals
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Journal of Nuclear Materials
›
top-articles
Journal of Nuclear Materials
2.8
(top 20%)
impact factor
29.6K
(top 1%)
papers
604.4K
(top 1%)
citations
180
(top 2%)
h
-index
2.8
(top 20%)
extended IF
31.8K
all documents
623.4K
doc citations
257
(top 2%)
g
-index
Top Articles
#
Title
Journal
Year
Citations
1
Handbook of SiC properties for fuel performance modeling
Journal of Nuclear Materials
2007
1,079
2
The chemical state of the fission products in oxide fuels
Journal of Nuclear Materials
1985
767
3
Accident tolerant fuels for LWRs: A perspective
Journal of Nuclear Materials
2014
754
4
Ferritic/martensitic steels for next-generation reactors
Journal of Nuclear Materials
2007
711
5
Perspective of ODS alloys application in nuclear environments
Journal of Nuclear Materials
2002
676
6
Recent analysis of key plasma wall interactions issues for ITER
Journal of Nuclear Materials
2009
671
7
Helium accumulation in metals during irradiation – where do we stand?
Journal of Nuclear Materials
2003
667
8
Structural materials for Gen-IV nuclear reactors: Challenges and opportunities
Journal of Nuclear Materials
2008
654
9
A full tungsten divertor for ITER: Physics issues and design status
Journal of Nuclear Materials
2013
618
10
Recent progress in research on tungsten materials for nuclear fusion applications in Europe
Journal of Nuclear Materials
2013
610
11
The rate theory of swelling due to void growth in irradiated metals
Journal of Nuclear Materials
1972
592
12
Tungsten as material for plasma-facing components in fusion devices
Journal of Nuclear Materials
2011
584
13
Thermophysical properties of uranium dioxide
Journal of Nuclear Materials
2000
568
14
Accident tolerant fuel cladding development: Promise, status, and challenges
Journal of Nuclear Materials
2018
560
15
Intragranular cellular segregation network structure strengthening 316L stainless steel prepared by selective laser melting
Journal of Nuclear Materials
2016
545
16
Materials for the plasma-facing components of fusion reactors
Journal of Nuclear Materials
2004
517
17
Structural materials challenges for advanced reactor systems
Journal of Nuclear Materials
2009
516
18
Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys
Journal of Nuclear Materials
2005
486
19
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
Journal of Nuclear Materials
2000
455
20
The effect of radiation upon diffusion in metals
Journal of Nuclear Materials
1978
454
21
Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys
Journal of Nuclear Materials
2005
445
22
Materials and processes for the effective capture and immobilization of radioiodine: A review
Journal of Nuclear Materials
2016
437
23
The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile material
Journal of Nuclear Materials
1959
436
24
Defect production in ceramics
Journal of Nuclear Materials
1997
415
25
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
Journal of Nuclear Materials
2014
403
26
Hydrogen isotope retention and recycling in fusion reactor plasma-facing components
Journal of Nuclear Materials
2002
401
27
Plasma facing and high heat flux materials – needs for ITER and beyond
Journal of Nuclear Materials
2002
397
28
Vacancy defect mobilities and binding energies obtained from annealing studies
Journal of Nuclear Materials
1978
393
29
A review of microstructure evolution in zirconium alloys during irradiation
Journal of Nuclear Materials
1988
392
30
Fuel corrosion processes under waste disposal conditions
Journal of Nuclear Materials
2000
388
31
Microstructure and mechanical properties of Inconel 625 superalloy
Journal of Nuclear Materials
2001
379
32
The relationship between hardness and yield stress in irradiated austenitic and ferritic steels
Journal of Nuclear Materials
2005
373
33
Lattice theory of point defects
Journal of Nuclear Materials
1978
372
34
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
Journal of Nuclear Materials
2014
368
35
The corrosion of uraninite under oxidizing conditions
Journal of Nuclear Materials
1992
367
36
The evolution of mechanical property change in irradiated austenitic stainless steels
Journal of Nuclear Materials
1993
367
37
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
Journal of Nuclear Materials
2013
363
38
Physics basis and design of the ITER plasma-facing components
Journal of Nuclear Materials
2011
361
39
Corrosion and stress corrosion cracking in supercritical water
Journal of Nuclear Materials
2007
359
40
Primary radiation damage: A review of current understanding and models
Journal of Nuclear Materials
2018
358
41
Low-activation ferritic and martensitic steels for fusion application
Journal of Nuclear Materials
1996
354
42
Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4
Journal of Nuclear Materials
1967
352
43
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
Journal of Nuclear Materials
2015
349
44
Radiation-induced segregation in binary and ternary alloys
Journal of Nuclear Materials
1979
346
45
Multidimensional multiphysics simulation of nuclear fuel behavior
Journal of Nuclear Materials
2012
346
46
Some aspects of the growth of diffusion layers in binary systems
Journal of Nuclear Materials
1961
335
47
The stability of precipitates in an irradiation environment
Journal of Nuclear Materials
1972
328
48
Radiation damage effects in zirconia
Journal of Nuclear Materials
1999
327
49
Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals
Journal of Nuclear Materials
1999
327
50
The primary damage state in fcc, bcc and hcp metals as seen in molecular dynamics simulations
Journal of Nuclear Materials
2000
326
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