Ion Cristescu

Karlsruhe Institute of Technology — Germany

Materials Science · Physical Sciences

17h-index931citations61works1.42yr avg
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Research Topics

Fusion materials and technologies(43), Nuclear reactor physics and engineering(18), Nuclear Materials and Properties(14), Muon and positron interactions and applications(12), Chemical Synthesis and Characterization(11)

Publications59 total

Tritium modeling, extraction, migration, and accountability
Elsevier eBooks·2024
Contributors
Elsevier eBooks·2024Open Access
Hydrogen extraction from a helium purge gas comparison of the ZrCo/ZAO getter material
Fusion Engineering and Design·2024· 2 citedOpen Access
Concept for HCPB TER using non-evaporable getters for tritium recovery
Fusion Engineering and Design·2024· 2 cited
Preliminary evaluation of NEG materials in view of CMSB replacement in HCPB TER architecture
Fusion Engineering and Design·2024· 3 cited
Construction of a Test Facility and the Test of an Active Tritium Permeation Barrier
Fusion Science & Technology·2023· 1 cited
Advancements in Designing the DEMO Driver Blanket System at the EU DEMO Pre-Conceptual Design Phase: Overview, Challenges and Opportunities
Journal of Nuclear Engineering·2023· 26 citedOpen Access
Tritium extraction and recovery system (TER) for the helium cooled pebble beds with steam in the helium purge gas
Fusion Engineering and Design·2023· 2 cited
Cryogenic bath-type heat exchangers for ultra-pure noble gas applications
Journal of Instrumentation·2022· 4 citedOpen Access
Status of maturation of critical technologies and systems design: Breeding blanket
Fusion Engineering and Design·2022· 90 citedOpen Access
Activities on Tritium Permeation and Barriers Developments to Mitigate the Releases from Fusion Devices
SSRN Electronic Journal·2022Open Access
Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design
Fusion Engineering and Design·2021· 34 citedOpen Access
Integration issues on tritium management of the European DEMO Breeding Blanket and ancillary systems
Fusion Engineering and Design·2021· 26 cited
Recent advances in tritium modeling and its implications on tritium management for outer fuel cycle
Fusion Engineering and Design·2020· 7 cited
Consolidated design of the HCPB Breeding Blanket for the pre-Conceptual Design Phase of the EU DEMO and harmonization with the ITER HCPB TBM program
Fusion Engineering and Design·2020· 90 cited
Developments on the tritium extraction and recovery system for HCPB
Fusion Engineering and Design·2020· 26 cited
Overview of the Tritium Technologies for the EU DEMO Breeding Blanket
Fusion Science & Technology·2020· 13 cited
Progress of the conceptual design of the European DEMO breeding blanket, tritium extraction and coolant purification systems
Fusion Engineering and Design·2020· 59 citedOpen Access
Assessment of Tritium Extraction and Removal System's Design Parameters for the DEMO-HCPB Breeding Blanket
Repository KITopen (Karlsruhe Institute of Technology)·2020Open Access
Cryogenic Hydrogen, Deuterium and Tritium at The Tritium Laboratory Karlsruhe
2020
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Frequent Co-authors

S. Welte(13), R. Michling(11), L.V. Boccaccini(9), Francisco A. Hernández(8), G.A. Spagnuolo(7), Marco Utili(6), M. Glugla(6), L. Dörr(6), P. Pereslavtsev(5), Guangming Zhou(5), Heiko Neuberger(5), Alessandro Del Nevo(5), D. Rapisarda(5), C. Day(5), Carlos Moreno(5), George Ana(5), C. Huhmann(5), M. Murra(5), I. Moscato(4), F. Cismondi(4)