ISSN: 0932-3902

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Kerntechnik Q3 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 21. It has an SJR impact factor of 0,26 and it has a best quartile of Q3. It is published in English. It has an SJR impact factor of 0,26.

Type: Journal

Type of Copyright:

Languages: English

Open Access Policy:

Type of publications:

Publication frecuency: -

Categories: Materials Science (miscellaneous) (Q3) Nuclear and High Energy Physics (Q3) Nuclear Energy and Engineering (Q3) Radiation (Q3) Safety, Risk, Reliability and Quality (Q3)

Price

- €

Inmediate OA

NPD

Embargoed OA

- €

Non OA

Metrics

0,26

SJR Impact factor

21

H Index

70

Total Docs (Last Year)

176

Total Docs (3 years)

1883

Total Refs

179

Total Cites (3 years)

175

Citable Docs (3 years)

1.22

Cites/Doc (2 years)

26.9

Ref/Doc

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MRS Communications Q3
Physics and Chemistry of Minerals Q3
Journal of Renewable Materials Q3
Aerosol Science and Engineering Q3
The European Physical Journal E Q3

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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

SHOW MORE ARTICLES

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