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%)
impact factor
31.8K
all documents
623.4K
doc citations
257(top 2%)
g-index

Top Articles

#TitleJournalYearCitations
1Handbook of SiC properties for fuel performance modelingJournal of Nuclear Materials20071,079
2The chemical state of the fission products in oxide fuelsJournal of Nuclear Materials1985767
3Accident tolerant fuels for LWRs: A perspectiveJournal of Nuclear Materials2014754
4Ferritic/martensitic steels for next-generation reactorsJournal of Nuclear Materials2007711
5Perspective of ODS alloys application in nuclear environmentsJournal of Nuclear Materials2002676
6Recent analysis of key plasma wall interactions issues for ITERJournal of Nuclear Materials2009671
7Helium accumulation in metals during irradiation – where do we stand?Journal of Nuclear Materials2003667
8Structural materials for Gen-IV nuclear reactors: Challenges and opportunitiesJournal of Nuclear Materials2008654
9A full tungsten divertor for ITER: Physics issues and design statusJournal of Nuclear Materials2013618
10Recent progress in research on tungsten materials for nuclear fusion applications in EuropeJournal of Nuclear Materials2013610
11The rate theory of swelling due to void growth in irradiated metalsJournal of Nuclear Materials1972592
12Tungsten as material for plasma-facing components in fusion devicesJournal of Nuclear Materials2011584
13Thermophysical properties of uranium dioxideJournal of Nuclear Materials2000568
14Accident tolerant fuel cladding development: Promise, status, and challengesJournal of Nuclear Materials2018560
15Intragranular cellular segregation network structure strengthening 316L stainless steel prepared by selective laser meltingJournal of Nuclear Materials2016545
16Materials for the plasma-facing components of fusion reactorsJournal of Nuclear Materials2004517
17Structural materials challenges for advanced reactor systemsJournal of Nuclear Materials2009516
18Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloysJournal of Nuclear Materials2005486
19Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposureJournal of Nuclear Materials2000455
20The effect of radiation upon diffusion in metalsJournal of Nuclear Materials1978454
21Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloysJournal of Nuclear Materials2005445
22Materials and processes for the effective capture and immobilization of radioiodine: A reviewJournal of Nuclear Materials2016437
23The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile materialJournal of Nuclear Materials1959436
24Defect production in ceramicsJournal of Nuclear Materials1997415
25Advanced oxidation-resistant iron-based alloys for LWR fuel claddingJournal of Nuclear Materials2014403
26Hydrogen isotope retention and recycling in fusion reactor plasma-facing componentsJournal of Nuclear Materials2002401
27Plasma facing and high heat flux materials – needs for ITER and beyondJournal of Nuclear Materials2002397
28Vacancy defect mobilities and binding energies obtained from annealing studiesJournal of Nuclear Materials1978393
29A review of microstructure evolution in zirconium alloys during irradiationJournal of Nuclear Materials1988392
30Fuel corrosion processes under waste disposal conditionsJournal of Nuclear Materials2000388
31Microstructure and mechanical properties of Inconel 625 superalloyJournal of Nuclear Materials2001379
32The relationship between hardness and yield stress in irradiated austenitic and ferritic steelsJournal of Nuclear Materials2005373
33Lattice theory of point defectsJournal of Nuclear Materials1978372
34Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effectsJournal of Nuclear Materials2014368
35The corrosion of uraninite under oxidizing conditionsJournal of Nuclear Materials1992367
36The evolution of mechanical property change in irradiated austenitic stainless steelsJournal of Nuclear Materials1993367
37High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environmentsJournal of Nuclear Materials2013363
38Physics basis and design of the ITER plasma-facing componentsJournal of Nuclear Materials2011361
39Corrosion and stress corrosion cracking in supercritical waterJournal of Nuclear Materials2007359
40Primary radiation damage: A review of current understanding and modelsJournal of Nuclear Materials2018358
41Low-activation ferritic and martensitic steels for fusion applicationJournal of Nuclear Materials1996354
42Terminal solubility and partitioning of hydrogen in the alpha phase of zirconium, Zircaloy-2 and Zircaloy-4Journal of Nuclear Materials1967352
43Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactorsJournal of Nuclear Materials2015349
44Radiation-induced segregation in binary and ternary alloysJournal of Nuclear Materials1979346
45Multidimensional multiphysics simulation of nuclear fuel behaviorJournal of Nuclear Materials2012346
46Some aspects of the growth of diffusion layers in binary systemsJournal of Nuclear Materials1961335
47The stability of precipitates in an irradiation environmentJournal of Nuclear Materials1972328
48Radiation damage effects in zirconiaJournal of Nuclear Materials1999327
49Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internalsJournal of Nuclear Materials1999327
50The primary damage state in fcc, bcc and hcp metals as seen in molecular dynamics simulationsJournal of Nuclear Materials2000326