Default: Nuclear Engineering and Technology

ISSN: 1738-5733

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Nuclear Engineering and Technology Q2 Unclaimed

Korean Nuclear Society South Korea
Unfortunately this journal has not been claimed yet. For this reason, some information may be unavailable.

Nuclear Engineering and Technology is a journal indexed in SJR in Nuclear Energy and Engineering with an H index of 60. It is an CC BY-NC-ND Journal with a Single blind Peer Review review system The scope of the journal is focused on reactor physics, nuclear safety, nuclear fuel cycle, nuclear fuel and reactor materials, radiation applications, nuclear I&C. It has an SJR impact factor of 0,693 and it has a best quartile of Q2. It is published in English. It has an SJR impact factor of 0,693.

Type: Journal

Type of Copyright: CC BY-NC-ND

Languages: English

Open Access Policy: Open Access

Type of publications:

Publication frecuency: -

Price

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

Nuclear Engineering and Technology

0,693

SJR Impact factor

60

H Index

534

Total Docs (Last Year)

1232

Total Docs (3 years)

17056

Total Refs

3675

Total Cites (3 years)

1232

Citable Docs (3 years)

2.84

Cites/Doc (2 years)

31.94

Ref/Doc

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Aims and Scope


Reactor physics Nuclear safety Nuclear fuel cycle Nuclear fuel and reactor materials Radiation applications Nuclear I&C



Best articles by citations

Hot cell renovation in the spent fuel conditioning process facility at the Korea Atomic Energy Research Institute

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DEVELOPMENT OF A VULNERABILITY ASSESSMENT CODE FOR A PHYSICAL PROTECTION SYSTEM: SYSTEMATIC ANALYSIS OF PHYSICAL PROTECTION EFFECTIVENESS (SAPE)

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PWSCC growth rate model of alloy 690 for head penetration nozzles of Korean PWRs

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Studying the operation of MOSFET RC-phase shift oscillator under different environmental conditions

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MICROSTRUCTURE AND MECHANICAL STRENGTH OF SURFACE ODS TREATED ZIRCALOY-4 SHEET USING LASER BEAM SCANNING

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A STUDY OF A NUCLEAR HYDROGEN PRODUCTION DEMONSTRATION PLANT

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INFLUENCE OF MECHANICAL ALLOYING ATMOSPHERES ON THE MICROSTRUCTURES AND MECHANICAL PROPERTIES OF 15Cr ODS STEELS

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A new approach for calculation of the neutron noise of power reactor based on Telegrapher's theory: Theoretical and comparison study between Telegrapher's and diffusion noise

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A novel analytical approach for advection diffusion equation for radionuclide release from an area source

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Spark plasma sintering of UO2 fuel composite with Gd2O3 integral fuel burnable absorber

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Development of a wireless radiation detection backpack using array silicon-photomultiplier (SiPM)

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A first-principles theoretical investigation of the structural, electronic and magnetic properties of cubic thorium carbonitrides ThCxN(1-x)

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A proposal on alternative sampling-based modeling method of spherical particles in stochastic media for Monte Carlo simulation

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Proposal of a prototype plant based on the exfoliation process for the treatment of irradiated graphite

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Gas detonation cell width prediction model based on support vector regression

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Raim -A model for iodine behavior in containment under severe accident condition

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Pipe thinning model development for direct current potential drop data with machine learning approach

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Effects of temperature and solution composition on evaporation of iodine as a part of estimating volatility of iodine under gamma irradiation

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Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor

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Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors

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Evaluation of the characteristics of the reflection plate to measure defects in the invisible area using infrared thermography

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APPLICATION OF BACKWARD DIFFERENTIATION FORMULA TO SPATIAL REACTOR KINETICS CALCULATION WITH ADAPTIVE TIME STEP CONTROL

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A Numerical Design and Feasibility Study of Self-Wastage Experiment Using Simulant Material in a Sodium Fast Reactor

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A STUDY ON ADSORPTION AND DESORPTION BEHAVIORS OF 14C FROM A MIXED BED RESIN

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