Author

Werner Maschek

Observed names: MASCHEK W., MASCHEK Werner, Maschek, W., W Maschek, W. Maschek, WERNER MASCHEK, Werner MASCHEK

Institution: Karlsruhe Institute of Technology

Observed institutions: Karlsruhe Institute of Technology, Forschungszentrum Küste

ORCID: 0000-0001-9068-6226

Observed ORCID: 0000-0001-9068-6226

OpenAlex ID: A5085601630

The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments

2006 · Y. Tobita, Sa. Kondo, et al. · Nuclear Technology · 97

Accelerator driven systems for transmutation: Fuel development, design and safety

2008 · W. Maschek, X. Chen, et al. · Progress in Nuclear Energy · 74

2006 · Shisheng Wang, Andrei Rineiski, et al. · Nuclear Engineering and Design · 49

Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code

2005 · Tohru Suzuki, Xue-Nong Chen, et al. · Nuclear Engineering and Design · 49

Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling

2007 · S. Wang, M. Flad, et al. · Progress in Nuclear Energy · 44

Thermophysical Properties of Lead-Bismuth Eutectic Alloy in Reactor Safety Analyses

2006 · Koji MORITA, Werner MASCHEK, et al. · Journal of Nuclear Science and Technology · 44

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Transverse buckling effects on solitary burn-up waves

2005 · Xue-Nong Chen, Werner Maschek · Annals of Nuclear Energy · 36

Transient analyses of the 400MWth-class EFIT accelerator driven transmuter with the multi-physics code: SIMMER-III

2010 · Ping Liu, Xuenong Chen, et al. · Nuclear Engineering and Design · 30

Simulation of central sloshing experiments with smoothed particle hydrodynamics (SPH) method

2011 · Alexander Vorobyev, Vladimir Kriventsev, et al. · Nuclear Engineering and Design · 27

Fundamental burn-up mode in a pebble-bed type reactor

2007 · Xue-Nong Chen, Edgar Kiefhaber, et al. · Progress in Nuclear Energy · 27

First 3-D calculation of core disruptive accident in a large-scale sodium-cooled fast reactor

2009 · Hidemasa Yamano, Yoshiharu Tobita, et al. · Annals of Nuclear Energy · 26

CERMET fuel behavior and properties in ADS reactors

2008 · D. Haas, A. Fernandez, et al. · Energy Conversion and Management · 26

Report on intermediate results of the IAEA CRP on ‘Studies of advanced reactor technology options for effective incineration of radioactive waste’

2008 · W. Maschek, A. Stanculescu, et al. · Energy Conversion and Management · 26

Fundamental solution of nuclear solitary wave

2012 · Xue-Nong Chen, Edgar Kiefhaber, et al. · Energy Conversion and Management · 24

ASTRID-like Fast Reactor Cores for Burning Plutonium and Minor Actinides

2015 · Fabrizio Gabrielli, Andrei Rineiski, et al. · Energy Procedia · 23

Minor actinide transmutation in ADS: the EFIT core design

2008 · C. Artioli, X. Chen, et al. · 23

Properties of cermet fuels for minor actinides transmutation in ADS

2006 · D. Haas, A. Fernandez, et al. · Energy Conversion and Management · 23

Kinetics models for safety studies of accelerator driven systems

2005 · A. Rineiski, W. Maschek · Annals of Nuclear Energy · 22

Application of safety analysis code SIMMER-IV to blockage accidents in FASTEF subcritical core

2013 · V. Kriventsev, A. Rineiski, et al. · Annals of Nuclear Energy · 21

Simulation of molten metal freezing behavior on to a structure

2008 · M. Mizanur Rahman, Yoshiyuki Ege, et al. · Nuclear Engineering and Design · 21

Prevention and mitigation of severe accident developments and recriticalities in advanced fast reactor systems

2011 · Werner Maschek, Michael Flad, et al. · Progress in Nuclear Energy · 20

ADS Fuel Developments in Europe: Results from the EUROTRANS Integrated Project.

2011 · F. Delage, R. Belin, et al. · Energy Procedia · 20

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Safety and design concepts of the 400MWth-class EFIT accelerator driven transmuter and considerations for further developments

2010 · W. Maschek, X.-N. Chen, et al. · Energy Conversion and Management · 20

Status and trend of core design activities for heavy metal cooled accelerator driven system

2006 · Fosco Bianchi, Carlo Artioli, et al. · Energy Conversion and Management · 20

Accident analyses and passive measures reducing the consequences of a core-melt in CAPRA/CADRA reactor cores

2000 · W Maschek, D Struwe · Nuclear Engineering and Design · 20

Works count: 113

Citation count: 1,224

H-index: 20

I10-index: 41