M. Zmítko

1.0k citations

46 papers · 804 indexed · h-index 16

Impact in

Materials Chemistry top 10%
- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear materials and radiation effects
Metals and Alloys top 10%

Papers in

Materials Chemistry 43
- Fusion materials and technologies 38
- Nuclear Materials and Properties 30
- Graphite, nuclear technology, radiation studies 6
- Nuclear materials and radiation effects 5
Metals and Alloys 2

Co-authors: Y. Poitevin I. Ricapito R. Rolli V. Chakin L. Giancarli Heiko Neuberger V.A. Chuyanov E. Rajendra Kumar
Journals: Fusion Engineering and Design (30 papers)Journal of Nuclear Materials (9 papers)Fusion Science & Technology (1 paper)Nuclear Materials and Energy (1 paper)Nuclear Engineering and Design (1 paper)
Partner nations: Spain Germany France

In The Last Decade

M. Zmítko

45 papers receiving 785 citations

Peers

Countries citing papers authored by M. Zmítko

Since Specialization

Citations

This map shows the geographic impact of M. Zmítko's research. It shows the number of citations coming from papers published by authors working in each country. You can also color the map by specialization and compare the number of citations received by M. Zmítko with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites M. Zmítko more than expected).

Fields of papers citing papers by M. Zmítko

Since Specialization

Physical SciencesHealth SciencesLife SciencesSocial Sciences

This network shows the impact of papers produced by M. Zmítko. Nodes represent research fields, and links connect fields that are likely to share authors. Colored nodes show fields that tend to cite the papers produced by M. Zmítko. The network helps show where M. Zmítko may publish in the future.

Co-authorship network

The 25 scholars most cited alongside M. Zmítko, linked wherever they have co-authored with each other. Click a name or a connecting line to browse the papers they share.

Border = papers with M. Zmítko Line = papers co-authored together M. Zmítko links everyone, so they are left out of the graph.

All Works

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20 of 20 papers shown

#	Work
1	Swelling of Highly Neutron Irradiated Beryllium and Titanium Beryllide SHILAP Revista de lepidopterología ·V. Chakin, А.А. Федоров, Ramil Gaisin, M. Zmítko	2022	5
2	The HICU PIE results of EU ceramic breeder pebbles: Tritium release properties Journal of Nuclear Materials ·Julia M. Heuser, Matthias Kolb, R. Rolli, H.-C. Schneider, Regina Knitter, M. Zmítko	2020	9
3	Development and qualification of functional materials for the European HCPB TBM Fusion Engineering and Design ·M. Zmítko, P. Vladimirov, Regina Knitter, Matthias Kolb, OB Edet, Julia M. Heuser, H.-C. Schneider, R. Rolli, V. Chakin, Barb Goode, D Lumsdon, А.А. Федоров, Y. Poitevin	2018	32
4	The European ITER Test Blanket Modules: Fabrication R&D progress for HCLL and HCPB Fusion Engineering and Design ·Laurent Forest, Yogendra Singh Varma, A. Li Puma, Mark W. Read, Teja Rus, M. Höck, M. Zmítko	2018	9
5	The European ITER Test Blanket Modules: EUROFER97 material and TBM’s fabrication technologies development and qualification Fusion Engineering and Design ·M. Zmítko, Pierre Sachot, Teja Rus, Perikles Simon, IVÁN ORELLANA A, Laurent Forest, Yogendra Singh Varma, G. Aiello, D. Flock, J. Rey, Heiko Neuberger, Jarir Aktaa, E. Gaganidze, Seong-Hyeon Lim, Daohui Cui, Choi Yeonyi, P. Lamagnère, Y. Poitevin	2017	27
6	Mechanical compression tests of beryllium pebbles after neutron irradiation up to 3000 appm helium production Fusion Engineering and Design ·V. Chakin, R. Rolli, A. Moeslang, M. Zmítko	2015	4
7	The European ITER Test Blanket Modules: Current status of fabrication technologies development and a way forward Fusion Engineering and Design ·M. Zmítko, Marion Damm, Teja Rus, Laurent Forest, Barbara Helen Albret, D. Flock, Yajun Chen, Heiko Neuberger, Y. Poitevin	2015	15
8	The European ITER test blanket modules: Progress in development of fabrication technologies towards standardization Fusion Engineering and Design ·M. Zmítko, Teja Rus, IVÁN ORELLANA A, Laurent Forest, D. Flock, Yajun Chen, Heiko Neuberger, Y. Poitevin	2015	9
9	Post irradiation characterization of beryllium and beryllides after high temperature irradiation up to 3000 appm helium production in HIDOBE-01 Fusion Engineering and Design ·А. В. Федоров, S. van Til, Giullyana Florentina Belchior, Masaru Nakamichi, M. Zmítko	2015	23
10	Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER Fusion Engineering and Design ·Y. Poitevin, I. Ricapito, M. Zmítko, F. Tavassoli, Teja Rus, Lismaniar, Emma McCann, J. Rey, Á. Ibarra, D. Panayotov, L. Giancarli, P. Calderoni, Marion Damm, Kalevi Heikura, A. Aiello	2014	23
11	Options and methods for instrumentation of Test Blanket Systems for experiment control and scientific mission Fusion Engineering and Design ·P. Calderoni, I. Ricapito, M. Zmítko, D. Panayotov, Kalevi Heikura, D. Leichtle, Y. Poitevin	2014	6
12	Tritium release and retention properties of highly neutron-irradiated beryllium pebbles from HIDOBE-01 experiment Journal of Nuclear Materials ·V. Chakin, R. Rolli, A. Moeslang, M. Klimenkov, Matthias Kolb, P. Vladimirov, P. Kurinskiy, H.-C. Schneider, S. van Til, 侯锡苗, M. Zmítko	2013	20
13	Characterization of constrained beryllium pebble beds after neutron irradiation at HFR at high temperatures up to helium production of 3000appm Fusion Engineering and Design ·V. Chakin, R. Rolli, A. Moeslang, P. Vladimirov, P. Kurinskiy, S. van Til, 侯锡苗, M. Zmítko	2013	14
14	Fracture toughness of the hydrogen charged EUROFER 97 RAFM steel at room temperature and 120°C Journal of Nuclear Materials ·猪三男桑原, Jan Berka, Jaroslav V. Burda, M. Zmítko	2009	12
15	Overview of the last progresses for the European Test Blanket Modules projects Fusion Engineering and Design ·J.-F. Salavy, L.V. Boccaccini, R. Lässer, R. Meyder, Heiko Neuberger, Y. Poitevin, G. Rampal, Émmanuel Rigal, M. Zmítko, A. Aiello	2007	27
16	ITER-Test blanket module functional materials Journal of Nuclear Materials ·C.P.C. Wong, В. М. Чернов, Akihiko Kimura, Yutai Katoh, N.B. Morley, T. Muroga, K. Song, Yifei Wu, M. Zmítko	2007	52
17	Corrosion product deposits on fuel cladding material M. Zmítko, 真一橋本, Emmauel Alor, Tomáš Matys Grygar, Ján Šubrt	1998	3
18	Hydrothermal reactions of corrosion products in reactor primary conditions M. Zmítko, Tomáš Matys Grygar, Václav Štengl, Ján Šubrt, V. L. Kantsyrev	1998	1
19	Primary coolant chemistry in VVER units Nuclear Engineering and Design ·真一橋本, M. Zmítko, 数夫小林, M. Jill Rosenbaum	1996	8
20	The effect of hydrazine dosing on high temperature water chemistry and corrosion product transport in primary circuit of VVER 440 units 李伟兵, Deise Martins Uriu, M. Zmítko, 真一橋本	1994	0

About M. Zmítko

M. Zmítko is a scholar working on Materials Chemistry, Metals and Alloys, Aerospace Engineering, Radiation and Safety, Risk, Reliability and Quality, having authored 46 papers that have together received 804 indexed citations. Recurring topics across this work include Fusion materials and technologies (38 papers), Nuclear Materials and Properties (30 papers), Nuclear reactor physics and engineering (17 papers), Graphite, nuclear technology, radiation studies (6 papers), Nuclear Physics and Applications (5 papers), Nuclear materials and radiation effects (5 papers), Superconducting Materials and Applications (4 papers) and Advanced materials and composites (4 papers). The work is most often cited by research in Materials Chemistry (715 citations), Metals and Alloys (29 citations), Aerospace Engineering (248 citations), Radiation (76 citations) and Nuclear and High Energy Physics (87 citations). M. Zmítko has collaborated with scholars based in Spain, Germany and France. Frequent co-authors include Y. Poitevin, I. Ricapito, R. Rolli, V. Chakin, L. Giancarli, Heiko Neuberger, V.A. Chuyanov, E. Rajendra Kumar, D. Campbell and Yu.S. Strebkov. Their work appears in journals such as Fusion Engineering and Design, Journal of Nuclear Materials, Fusion Science & Technology, Nuclear Materials and Energy and Nuclear Engineering and Design.

Rankless uses publication and citation data sourced from OpenAlex, an open and comprehensive bibliographic database. While OpenAlex provides broad and valuable coverage of the global research landscape, it—like all bibliographic datasets—has inherent limitations. These include incomplete records, variations in author disambiguation, differences in journal indexing, and delays in data updates. As a result, some metrics and network relationships displayed in Rankless may not fully capture the entirety of a scholar's output or impact.

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