Nuclear Engineering and Design
Nuclear Engineering and Design is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 129. It has an SJR impact factor of 0,772 and it has a best quartile of Q1. It is published in English. It has an SJR impact factor of 0,772.
Metrics
Scimago and CountryOfPapers database fields
SJR Impact
0,772
H-index
129
Docs (year)
822
Docs 3y
1446
Total refs
30298
Cites 3y
3561
Citable 3y
1438
Cites/Doc 2y
2.36
Ref/Doc
36.86
Immediate OA
—
Embargoed OA
NPD
Non OA / Submission
—
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Researcher reviews
Best articles by citations
Cooling elements for passive heat removal
View moreWeld metal creep-fatigue life prediction by modeling the microstructure degradation due to the exposure to high temperature and load
View moreEngineering failure assessment methods applied to pressurised components
View moreEC-sponsored research activities on innovative passive safety systems
View moreDynamic response analysis of tube array in calandria to rotational vault motion
View moreDouble-supply-frequency pressure pulsation in annular linear induction pump, part II: reduction of pulsation by linear winding grading at both stator ends
View moreDimensionally adaptive dynamic switching and adjoint sensitivity analysis: new features of the RELAP5/PANBOX/COBRA code system for reactor safety transients
View moreDevelopment of passive safety systems for Next Generation PWR in Japan
View moreDevelopment of a PFM code for evaluating reliability of pressure components subject to transient loading
View moreDesign and corrosion study of a closed spallation target module of an accelerator-driven system (ADS)
View moreDefense-in-depth and diversity evaluation to cope with design bases events concurrent with common mode failure in digital plant protection system for KNGR
View moreCyclic plastic deformation tests to verify FEM-based shakedown analyses
View moreCracking and fracture of valve shafts in the secondary steam circuit of a nuclear power plant. A case investigation.
View moreA model for predicting vessel failure probabilities including the effects of service inspection and flaw sizing errors
View moreControlling and cooling core melts outside the pressure vessel
View moreConservatism of ASME KIR-reference curve with respect to crack arrest
View moreCalculation of fission product behaviour in an advanced containment in case of a severe accident
View moreCalculation method for diffusional gas release with grain boundary resolution
View moreBoron mixing in complex geometries: flow structure details
View moreAnalysis of steam and hydrogen distributions with PAR mitigation in NPP containments
View moreAnalysis of high burnup fuel behavior in Halden reactor by FEMAXI-V code
View moreAn investigation on the green properties of U-10wt.%Mo/Al and U3Si2/Al powder compacts
View moreAn approach to the assessment of high-level radioactive waste containment. I: Waste package degradation
View moreAchievements and further plans for the OECD Halden reactor project materials programme
View more