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verified SJR 0,657 · Q2 • database Scopus / SJR & Web of Science indexed
Nuclear Science and Engineering
United States · Taylor and Francis Ltd.
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Nuclear Science and Engineering

Nuclear Science and Engineering is a journal indexed in SJR in Nuclear Energy and Engineering with an H index of 68. It has an SJR impact factor of 0,657 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,657.

ISSN: 0029-5639
Publisher: Taylor and Francis Ltd.
Category: Nuclear Energy and Engineering
Indexation: verifiedScopus / SJR verifiedWeb of Science
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schedule CountryOfPapers database fields
SJR Impact Factor trending_up
0,657 Q2
H-index 68
Acceptance rate pie_chart
29% Selective
Source Acceptance_Rate
Time to publication hourglass_top
NPD
Field NPD
Publication cost (APC) payments
NPD Subscription
Non-OA path NPD

Metrics

Scimago and CountryOfPapers database fields

Scopus / SJR Web of Science

SJR Impact

0,657

H-index

68

Docs (year)

273

Docs 3y

419

Total refs

7829

Cites 3y

673

Citable 3y

406

Cites/Doc 2y

1.54

Ref/Doc

28.68

Immediate OA

—

Embargoed OA

NPD

Non OA / Submission

—

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Best articles by citations

An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors

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Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Startup Operations

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Coupled Fast-Thermal Power Breeder

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Corrosion of Materials by Liquid NaK Coolant in a Nuclear Power System

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Confidence Interval Procedures for Monte Carlo Transport Simulations

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Computation of Continuous-Energy Neutron Spectra with Discrete Ordinates Transport Theory

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Characteristics, Stability, and Short-Wavelength Phenomena in Two-Phase Flow Equation Systems

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Characteristics and Stability Analyses of Transient One-Dimensional Two-Phase Flow Equations and Their Finite Difference Approximations

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Calculation of Higher-Order Fluxes in Symmetric Cores - I: Theory

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B&W Spectral Shift Control Reactor Lattice Experiments: Evaluation of Core I and Core VIII

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Application of the Probability Table Method to Multigroup Calculations of Neutron Transport

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Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant-Interaction Code TEXAS-VI

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Advanced Studies and Statistical Treatment for Sodium-Cooled Fast Reactor Pin Failures During Unprotected Transient Overpower Accident

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