ISSN: 0932-3902

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Kerntechnik Q4 Unclaimed

Walter de Gruyter GmbH Germany

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Kerntechnik is a journal indexed in SJR in Materials Science (miscellaneous) and Nuclear Energy and Engineering with an H index of 20. It has an SJR impact factor of 0,197 and it has a best quartile of Q4. It is published in English. It has an SJR impact factor of 0,197.

Type: Journal

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

Categories: Materials Science (miscellaneous) (Q4) Nuclear and High Energy Physics (Q4) Nuclear Energy and Engineering (Q4) Radiation (Q4) Safety, Risk, Reliability and Quality (Q4)

Price

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,197

SJR Impact factor

20

H Index

64

Total Docs (Last Year)

169

Total Docs (3 years)

1922

Total Refs

84

Total Cites (3 years)

164

Citable Docs (3 years)

0.62

Cites/Doc (2 years)

30.03

Ref/Doc

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Other journals with similar parameters

Solid State Phenomena Q4
Journal of Physical Science Q4
Digest Journal of Nanomaterials and Biostructures Q4
Radiation Effects and Defects in Solids Q4
Zhidkie Kristally i Ikh Prakticheskoe Ispol'zovanie Q4

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Aims and Scope

Best articles by citations

Inter-assembly gap deviations in VVER-1000: Accounting for effects on engineering margin factors

SIMULATE-3 K coupled code applications

Numerical method improvement for a subchannel code

Experimental and computational investigations of heat and mass transfer of intensifier grids

Study of the response reduction of LiF:Mg, Ti dosimeter for high dose dosimetry

Development of a new analytic function expansion nodal code, HexDANM, for solving the neutron diffusion equation in hexagonal-Z geometry

Study on effects of mixing vane grids on coolant temperature distribution by subchannel analysis

Laser cleaning of steam generator tubing based on acoustic emission technology

CFD analysis on mixing effects of spacer grids with different dimples and sizes for advanced fuel assemblies

Reflood experiments in rod bundles with flow blockages due to clad ballooning

Investigation of neutronic behavior in a CANDU reactor with different (Am, Th,235U)O2fuel matrixes

Challenges in reactor core thermal-hydraulics: subchannel analysis, CFD modeling and rod bundle CHF

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An investigation of the effect of the upper beryllium reflector on the moderator temperature coefficient of reactivity of miniature neutron source reactors

T1andU1approximations to neutron transport equation in one-dimensional spherical geometry

Sensitivity analysis for thermo-hydraulics model of a Westinghouse type PWR: verification of the simulation results

Evaluation of gross radioactivity in foodstuffs

Shamir Secret Sharing Scheme with Dynamic Access Structure (SSSDAS): case study on nuclear power plant

CFD evaluation on the thermohydraulic characteristics of tube support plates in steam generator

Research on the reactor physics and reactor safety of VVER reactors -AER Symposium 2014

Sensitivity study with respect to direction of ADI method during re-flooding in AHWR

Assessment of the uncertainties of MULTICELL calculations by the OECD NEA UAM PWR pin cell burnup benchmark

Multiple condensation induced water hammer events, experiments and theoretical investigations

A comparison study for mass attenuation coefficients of some amino acids using MCNP code

Analyses of Beyond Design Basis Accident Homogeneous Boron Dilution Scenarios