ISSN: 0029-5493

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Nuclear Engineering and Design Q1 Unclaimed

Elsevier BV Netherlands

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Nuclear Engineering and Design is a journal indexed in SJR in Materials Science (miscellaneous) and Mechanical Engineering with an H index of 115. It has an SJR impact factor of 0,853 and it has a best quartile of Q1. It is published in English. It has an SJR impact factor of 0,853.

Type: Journal

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

Categories: Materials Science (miscellaneous) (Q1) Mechanical Engineering (Q1) Nuclear Energy and Engineering (Q1) Safety, Risk, Reliability and Quality (Q1) Nuclear and High Energy Physics (Q2) Waste Management and Disposal (Q2)

Price

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,853

SJR Impact factor

115

H Index

404

Total Docs (Last Year)

1347

Total Docs (3 years)

13256

Total Refs

2659

Total Cites (3 years)

1330

Citable Docs (3 years)

1.88

Cites/Doc (2 years)

32.81

Ref/Doc

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Advanced Energy Materials Q1
Progress in Materials Science Q1
Materials Science and Engineering: R: Reports Q1
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Aims and Scope

Best articles by citations

A model for predicting vessel failure probabilities including the effects of service inspection and flaw sizing errors

Dimensionally adaptive dynamic switching and adjoint sensitivity analysis: new features of the RELAP5/PANBOX/COBRA code system for reactor safety transients

Preface

Defense-in-depth and diversity evaluation to cope with design bases events concurrent with common mode failure in digital plant protection system for KNGR

Dynamic response analysis of tube array in calandria to rotational vault motion

Mechanistic modeling for ring-type BWR fuel spacer design

Mechanistic modeling for ring-type BWR fuel spacer design 2. Local pressure drop and narrow channel effect

Root cause analysis of operational induced vibrations in a feedwater system

Static strength analysis of CANDU-6 reactor fuel bundle

An approach to the assessment of high-level radioactive waste containment. I: Waste package degradation

Thermal hydraulics of PWRS with respect to boron dilution phenomena. Experimental results from the test facilities PKL and UPTF

The nuclear safety research project

SHOW MORE ARTICLES

Remote sensing for flow induced vibrations in the PARR-1 core assembly

Reflooding experiments with LWR-type fuel rod simulators in the QUENCH facility

Calculation method for diffusional gas release with grain boundary resolution

New applications using phased array techniques

Statistical model for the random cyclic strain-life relations of 1Cr18Ni9Ti pipe-weld metal under temperature of 240ºC

Cooling elements for passive heat removal

The FEM based calculation of crack-tip strain rate for determining the crack growth rate of 304 stainless steel in BWR environments

Design and corrosion study of a closed spallation target module of an accelerator-driven system (ADS)

A study on the connection effects of subsurface slabs to exterior walls in the KNGR seismic analysis

Stability analysis of single-phase thermosyphon loops by finite-difference numerical methods

Structure mechanics and thermal-hydraulic behaviour of a PWR coolant loop with a postulated crack like leakage

Flow excursion phenomenon and its mechanism in natural circulation