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Institution · Framatome (Germany)

Most cited papers from Framatome (Germany)

Framatome (Germany)

What are the most cited papers from Framatome (Germany)?

The most cited paper from Framatome (Germany) is "Precoding in Multiantenna and Multiuser Communications" (Christoph Windpassinger, Robert F. H. Fischer, T. Vencel et al., 2004), with 558 citations. Next come "The ERANOS Code and data system for fast reactor neutronic analyses" (248) and "The European power plant conceptual study" (147).

Showing 50 of 58 papers. Every paper with more than 21 citations is listed.

Most cited papers, sortable by citations and release date
#Paper
1 Precoding in Multiantenna and Multiuser Communications Christoph Windpassinger, Robert F. H. Fischer, T. Vencel et al. · IEEE Transactions on Wireless Communications Jul 2004 558
2 The ERANOS Code and data system for fast reactor neutronic analyses G. Rimpault, Danièle Plisson, J. Tommasi et al. · HAL (Le Centre pour la Communication Scientifique Directe) Conference paperOpen access 7 Oct 2002 248
3 The European power plant conceptual study David Maisonnier, I. Cook, Pierre Sardain et al. · Fusion Engineering and Design 26 Jul 2005 147
4 High performance light water reactor David Squarer, Thomas S. Schulenberg, D. Struwe et al. · Nuclear Engineering and Design 26 Mar 2003 145
5 Generic approach for designing and implementing a passive autocatalytic recombiner PAR-system in nuclear power plant containments E Bachellerie, F. Arnould, Miche`le Auglaire et al. · Nuclear Engineering and Design 26 Mar 2003 132
6 The influence of different alloying elements on the development of the γ/γ′ microstructure of nickel-base superalloys during high-temperature annealing and deformation Florian Pyczak, Bastian Devrient, F.C. Neuner et al. · Acta Materialia 30 Jun 2005 120
7 Matrix swelling rate and cavity volume balance of UO2 fuels at high burn-up José Luis Spino, Jeffrey Rest, Wolfgang Goll et al. · Journal of Nuclear Materials 16 Sep 2005 113
8 Long time experience with the development of HTR fuel elements in Germany H. Nickel, Heinz Nabielek, G. Pott et al. · Nuclear Engineering and Design Aug 2002 110
9 EPMA and SEM of fuel samples from PWR rods with an average burn-up of around 100 MWd/kgHM R. Manzel, C.T. Walker · Journal of Nuclear Materials Mar 2002 109
10 The Effects of Different Alloying Elements on the Thermal Expansion Coefficients, Lattice Constants and Misfit of Nickel-Based Superalloys Investigated by X-Ray Diffraction Florian Pyczak, B. Devirent, Haël Mughrabi Conference paperOpen access 2004 105
11 The severe accident mitigation concept and the design measures for core melt retention of the European Pressurized Reactor (EPR) Manfréd M. Fischer · Nuclear Engineering and Design 19 Mar 2004 104
12 The low spin - high spin equilibrium in the S2-state of the water oxidizing enzyme Alain Boussac, İlke Uǧur, Antoine Marion et al. · Biochimica et Biophysica Acta (BBA) - Bioenergetics Open access 27 Feb 2018 103
13 2000 F.N. Speller Award Lecture: Stress Corrosion Cracking in Pressurized Water Reactors—Interpretation, Modeling, and Remedies Peter Manley Scott · CORROSION Aug 2000 95
14 On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM C.T. Walker, D. Staicu, Michael Sheindlin et al. · Journal of Nuclear Materials 20 Jan 2006 87
15 A Review of Corrosion of Titanium Grade 7 and Other Titanium Alloys in Nuclear Waste Repository Environments Fuan Hua, K. Mon, Pasu Pasupathi et al. · CORROSION Oct 2005 85
16 Differences in reactivity of oxide growth during the oxidation of Zircaloy-4 in water vapour before and after the kinetic transition Marc Tupin, M. Pijolat, F. Valdivieso et al. · Journal of Nuclear Materials 7 Apr 2003 80
17 Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility Jean-Christophe Brachet, Matthieu Le Saux, Jeffrey E. Bischoff et al. · Journal of Nuclear Materials Open access 13 Mar 2020 77
18 Design analysis of core assemblies for supercritical pressure conditions Cheng Xu, Thomas S. Schulenberg, Dietmar Bittermann et al. · Nuclear Engineering and Design 7 Apr 2003 77
19 Comparison of the High Burn-Up Corrosion on M5 and Low Tin Zircaloy-4 Philippe Bossis, Dominique Pêcheur, Karine HANIFI et al. · Journal of ASTM International 21 Sep 2005 74
20 Integral large scale experiments on hydrogen combustion for severe accident code validation-HYCOM W. Breitung, S.B. Dorofeev, A. Kotchourko et al. · Nuclear Engineering and Design 15 Dec 2004 69
21 X-ray macrostress determination on textured material; use of the ODF for calculating the X-ray compliances M.C. Barral, J. L. Lebrun, Jean‐Michel Sprauel et al. · Metallurgical Transactions A Jul 1987 68
22 European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE) Daniel Mora Magallón et al. · Nuclear Engineering and Design 15 Dec 2004 62
23 Phase diagram of the ZrO2–FeO system Sevostian Bechta, Е.В. Крушинов, V.I. Almjashev et al. · Journal of Nuclear Materials 18 Nov 2005 62
24 Influence of Hydrogen Content on the α/β Phase Transformation Temperatures and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5™ (ZrNbO) Alloys During the First Phase of LOCA Transient J-C Brachet, Laurence Portier, T. Forgeron et al. Conference paper 2002 62
25 Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys D. Gilbon, A Soniak, Sylvie Doriot et al. Conference paper 2000 61
26 On the oxidation state of UO2 nuclear fuel at a burn-up of around 100MWd/kgHM C.T. Walker, V.V. Rondinella, Dimitri Papaioannou et al. · Journal of Nuclear Materials 21 Jul 2005 60
27 Open-Source MQTT Evaluation Melvin Bender, Erkin Kirdan, Marc‐Oliver Pahl et al. Conference paper 9 Jan 2021 58
28 Towards cross-commodity energy-sharing communities – A review of the market, regulatory, and technical situation Satu Paiho, Jussi Kiljander, Roope Sarala et al. · Renewable and Sustainable Energy Reviews Open access 17 Aug 2021 50
29 Iodine behaviour under LWR accident conditions: Lessons learnt from analyses of the first two Phebus FP tests N. Girault, S. Dickinson, Friedhelm Funke et al. · Nuclear Engineering and Design 4 Feb 2006 48
30 A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor J.M. Paratte, René FRÜH, U. Kasemeyer et al. · Annals of Nuclear Energy Open access May 2006 47
31 Contribution to the Understanding of the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding Dominique Pêcheur, J. Godlewski, Jean Peybernès et al. Conference paper 2000 46
32 Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 and M5Framatome alloys Matthieu Le Saux, Jean-Christophe Brachet, Valérie Vandenberghe et al. · Journal of Nuclear Materials Open access 19 Mar 2019 39
33 Corrosion behaviour of reactor coolant system materials in nuclear power plants Renate Kilian, Armin Roth · Materials and Corrosion Oct 2002 39
34 Experimental and Numerical Investigation of Boron Dilution Transients in Pressurized Water Reactors R. Hertlein, Klaus Umminger, S. Kliem et al. · Nuclear Technology 2003 38
35 Study of the Mechanisms Controlling the Oxide Growth Under Irradiation: Characterization of Irradiated Zircaloy-4 and Zr-1Nb-O Oxide Scales Philippe Bossis, J Thomazet, Florence Lefebvre-Joud Conference paper 2002 34
36 An Overview of Superphénix Commissioning Tests J. Gourdon, Bernard. Mesnage, J. L. Voitellier et al. · Nuclear Science and Engineering Sep 1990 32
37 Demonstration of the heat removing capabilities of the EPR core catcher Manfréd M. Fischer, Oliver Herbst, Holger Schmidt · Nuclear Engineering and Design 29 Apr 2005 32
38 Thermal response of a modular high temperature reactor during passive cooldown under pressurized and depressurized conditions H.M. Enamul Haque, W. Feltes, Gerd Brinkmann · Nuclear Engineering and Design 31 Jan 2006 32
39 Open-Source OPC UA Security and Scalability Nikolas Mühlbauer, Erkin Kirdan, Marc‐Oliver Pahl et al. Conference paper Sep 2020 30
40 Study of Nb and Fe Precipitation in α-Phase Temperature Range (400 to 550°C) in Zr-Nb-(Fe-Sn) Alloys Caroline Toffolon-Masclet, Pierre Barbéris, J-C Brachet et al. Conference paper 2005 30
41 Optimization of PWR Behavior of Stress-Relieved Zircaloy-4 Cladding Tubes by Improving the Manufacturing and Inspection Process J-P Mardon, Daniel CHARQUET, J. Senevat Conference paper 1994 29
42 Modeling the hydrogen-induced cracking of titanium alloys in nuclear waste repository environments Fred Hua, Pasu Pasupathi, K. Mon et al. · JOM Open access 2005 29
43 Benchmark DEBORA: Assessment of MCFD compared to high-pressure boiling pipe flow measurements Guillaume Bois et al. · International Journal of Multiphase Flow Open access 29 Jul 2024 26
44 Towards a Real-Time Environment Reconstruction for VR-Based Teleoperation Through Model Segmentation Sebastian Kohn, Andreas Blank, David Puljiz et al. Conference paper Oct 2018 26
45 Models for reactor physics calculations for HTR pebble bed modular reactors W. Bernnat, W. Feltes · Nuclear Engineering and Design May 2003 26
46 Restart of natural circulation in a PWR–PKL test results and s-relap5 calculations Klaus Umminger, R.M. Mandl, R.E. Wegner · Nuclear Engineering and Design Jun 2002 26
47 The DEEPSSI project, design, testing and modeling of steam injectors Patrick Dumaz, G. Geffraye, Vladimir Kalitvianski et al. · Nuclear Engineering and Design 15 Dec 2004 24
48 Temperature dependence of the electrochemical behavior of the 690 Ni-base alloy between 25 and 325 °C Salma El Euch, Damien Bricault, Hubert Cachet et al. · Electrochimica Acta Open access 28 May 2019 23
49 Field Test of Water-Steam Separators for Direct Steam Generation in Parabolic Troughs Markus Eck, Holger Schmidt, Martin Eickhoff et al. · Journal of Solar Energy Engineering 28 Dec 2007 23
50 Multi-dimensional simulation of hydrogen distribution and turbulent combustion in severe accidents Ulrich Bielert, W. Breitung, A. Kotchourko et al. · Nuclear Engineering and Design Nov 2001 23

Citations are OpenAlex's own counts, from its 2026-09-23 snapshot, so the ranking can differ from Google Scholar or Web of Science. A paper is listed for an institution when any of its authors gave it as an affiliation; retracted papers and papers whose citation count cannot be traced to citing works are left out, and a preprint and the article it became are shown once. Release dates are OpenAlex's: where a source gave only a month or a year, that is what is shown. How the lists are chosen.