Joint European Canadian Chinese development of Small Modular Reactor Technology

CORDIS fournit des liens vers les livrables publics et les publications des projets HORIZON.

Les liens vers les livrables et les publications des projets du 7e PC, ainsi que les liens vers certains types de résultats spécifiques tels que les jeux de données et les logiciels, sont récupérés dynamiquement sur OpenAIRE .

Livrables

Safety criteria and requirements for the SCW-SMR concept

The basic safety criteria and requirements already exist aiming at minimizing the risk of accidents. As a first step, a compilation of the basic general safety criteria and requirements for SMRs contained in the relevant documents of the IAEA and GIF will be used as a starting point to develop the specific safety criteria and requirements for the SCC-SMR concept. Experience from the SMR ENERGY WELL design & implementation will be used. In particular, the concepts of defence-in-depth, physical protection and security, and non-proliferation principles (safety, security and safeguards) will be described in this deliverable.

Report on the pre-conceptual studies on the core layout and passive safety concept of the SCW-SMR

The report will summarise the results of the pre-conceptual studies on the core layout and passive safety concept of the SCW-SMR as elaborated during the work performed in the WPs of the project.

Training material -booklet & presentations

Designing and compiling the information developed for training in the format of a booklet and presentation materials. This document is important in the dissemination process.

Guidelines for the demonstration of the safety of the SCW-SMR concept

Guidelines and instructions for the future demonstration of the safety of the SCW-SMR concept will be described. Emphasis will be given to the safety criteria and requirements, for which the task WP5.3 will claim that (2) fulfilment is probable, but further research is needed, and (3) fulfilment is improbable, design changes are needed. Also, the future experimental efforts necessary for successful licensing will be described in some detail.

Report on the results of the benchmark exercise

Describing the benchmark setup, calculated results and code ability assessment

Report on CFD modelling and simulations in corroded environment under supercritical conditions

The report will summarise the results of CFD modelling and simulations in a corroded environment under supercritical conditions achieved within the framework of the project.

Safety related features of the SCW-SMR concept

The aim of this deliverable is to provide answers to the potentially outstanding issues and gaps in knowledge regarding the safety related behavior of supercritical water reactor. The outcome of this task will summarize the conclusions and lessons learned into a synthetic form to facilitate the future work of designers and nuclear safety analysts

Report on pre-conceptual design requirements for ECC SCW-SMR

The current nuclear systems have been considered too big for small and remote communities, as well as mining and military establishments. Small modular reactors (SMRs) have been proposed as alternatives to support these niche applications. Main advantages of SMRs include reductions in capital cost and construction time as well as enhanced flexibility to design reactor output for meeting the local deployment strategy. Many SMR concepts have been proposed or under development. These concepts include pressurized water-cooled reactors, sodium-cooled fast reactors, molten-salt reactors, lead-cooled fast reactors and high-temperature gas-cooled reactors. SMRs based on pressurized water-cooled reactors have been advancing rapidly (e.g., SMART from South Korea and CAREM from Argentina are under construction and NuScale from the USA are planning the construction of their first plant in 2024). SMRs based on other reactor types are still in the conceptual design phase.The goal of this report is to establish a list of requirements for the pre-conceptualization of a small modular reactor (SMR) operating with water at supercritical conditions. Some of the important points that the list should be based on are: •Enhanced safety, Lower Financial risks, Better Economy, Cost to build Infrastructure, Proliferation resistance.

Report summarising the newly generated reference data for natural convection, forced and mixed convection and decay heat removal

The report will summarise the newly generated reference data for forced and mixed convection and decay heat removal achieved within the framework of the ECC-SMART project.

Report on the improved system codes describing how they improved

Report Describing the code ability and validation, simulated conditions and results discussions

Pre-licensing study

The pre-licensing study will relate the safety criteria and requirements for the SCW-SMR concept developed in WP5.1 with the safety-related behavior and features of the SCW-SMR as identified in WP5.2 and to the available level of detail. No specific experimental verifications are planned for this pre-licensing study It is expected that this study will identify three sets of the safety criteria and requirements: (1) fulfilled with reasonable certainty within the limits of already available knowledge, (2) fulfilment is probable, further research needed, and (3) fulfilment is improbable, design changes are needed.

Report on visits of PhD students/post-docs/young scientists

At the end of the project, a report will be produced on the stages the PhDs, students post-docs and young scientists performed within the framework of the project.

Proceedings of workshop on thermal hydraulics and neutronics of the SCW-SMR

Elaboration of proceedings for a workshop on thermal-hydraulics and neutronics where findings related to the pre-licensing studies and the guidelines for the demonstration of the safety of the SCC-SMR concept will be presented.

Proceedings of the ISSCWR

Book of proceedings of the ISSCWR-10 conference.

Proceedings of workshop on materials and online in-situ methods for corrosion monitoring in SCWR

Elaboration of proceedings for a workshop on materials and in-situ methods for corrosion monitoring where findings related to the pre-licensing studies and the guidelines for the demonstration of the safety of the SCC-SMR concept will be presented.

Project presentation

The overall presentation of the project. To be presented at the kick-off meeting and used for further project PR purposes.

Publications

Coupled reactor physics and thermal-hydraulics analysis of an SCW-SMR reactor concept – Part I: Model development and demonstration

Auteurs: Tamás Varju, Boglárka Babcsány, Péter Mészáros, Csenge Antók, Szabolcs Czifrus
Publié dans: Annals of Nuclear Energy, 2025, Page(s) 111222, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2025.111222

Measurement system for in-situ estimation of instantaneous corrosion rate in supercritical water

Auteurs: Jaromír Valtr, Petr Roztočil, David Dašek, Radek Mušálek, František Lukáč, Jakub Klečka, Marek Janata, Mariana Arnoult-Růžičková, Eva Mištová, Luděk Jelínek, Petr Sajdl, Jan Macák
Publié dans: The Journal of Supercritical Fluids, Numéro 204, 2023, Page(s) 106091, ISSN 0896-8446
Éditeur: Elsevier BV
DOI: 10.1016/j.supflu.2023.106091

Discussion and perspectives for improvements of heat transfer correlation capabilities for fluids at supercritical pressures

Auteurs: T. Varju, A. Csige, A. Kiss, V. Filonov, Y. Filonova, D. Fedorov, A. Pucciarelli, S. Kassem, W. Ambrosini
Publié dans: Nuclear Engineering and Design, Numéro 421, 2024, Page(s) 113085, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2024.113085

Initial Multidisciplinary Study of Oxidized Chromium-Coated Zirconium Alloy for Fuel Cladding of SCW-SMR Concept: Weight-Gain and Thermal Conductivity Measurements and Coating Cost Evaluation

Auteurs: Kittima Khumsa-Ang, Alberto Mendoza, Armando Nava-Dominguez, Chukwudi Azih, Hussam Zahlan
Publié dans: Coatings, Numéro 13, 2023, Page(s) 1648, ISSN 2079-6412
Éditeur: MDPI AG
DOI: 10.3390/coatings13091648

Overview of a Theory for Planning Similar Experiments with Different Fluids at Supercritical Pressure

Auteurs: Andrea Pucciarelli, Sara Kassem and Walter Ambrosini
Publié dans: Energies 2021, 14(12), 3695; https://doi.org/10.3390/en14123695, 2021, ISSN 1996-1073
Éditeur: Multidisciplinary Digital Publishing Institute (MDPI)
DOI: 10.3390/en14123695

Results and lessons learned from the Generation IV SCWR-FQT comprehensive Monte Carlo computational benchmark

Auteurs: Boglárka Babcsány, Valerio Giusti, Andreea Moise, Péter Mészáros, Szabolcs Czifrus, Jimmy C. Chow
Publié dans: Annals of Nuclear Energy, Numéro Volume 191, October 2023, 109903, 2023, Page(s) 19, ISSN 1873-2100
Éditeur: Elsevier Ltd.
DOI: 10.1016/j.anucene.2023.109903

Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors

Auteurs: Haodong Jia, Yingjie Wang, You Wang, Lu Han, Yujuan Zhang, Zhangjian Zhou
Publié dans: Materials, Numéro 16, 2025, Page(s) 3497, ISSN 1996-1944
Éditeur: MDPI Open Access Publishing
DOI: 10.3390/ma16093497

Coupled reactor physics and thermal-hydraulics analysis of an SCW-SMR reactor concept – Part II: Improvement of the concept and sensitivity analyses

Auteurs: Tamás Varju, Csenge Antók, Péter Mészáros, Boglárka Babcsány
Publié dans: Annals of Nuclear Energy, 2025, Page(s) 111221, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2025.111221

On the Limitations of Positron Annihilation Spectroscopy in the Investigation of Ion-Implanted FeCr Samples

Auteurs: Vladimir Slugen, Jarmila Degmova, Stanislav Sojak, Martin Petriska, Pavol Noga and Vladimir Krsjak
Publié dans: Metals, 2021, ISSN 2075-4701
Éditeur: MDPI
DOI: 10.3390/met11111689

General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C

Auteurs: K. Khumsa-Ang, M. Edwards, S. Rousseau
Publié dans: Journal of Nuclear Engineering and Radiation Science, Numéro 6, 2020, ISSN 2332-8983
Éditeur: Journal of Nuclear Engineering and Radiation Science
DOI: 10.1115/1.4045387

A new approach to near-surface positronannihilation analysis of ion irradiated ferritic alloys

Auteurs: Vladimir Krsjak, Petr Hruska, Jarmila Degmova, Stanislav Sojak, Pavol Noga, Tielong Shen, Veronika Sabelova, Werner Eggere and Vladimir Slugen
Publié dans: Nanoscale Advances, 2021, ISSN 2516-0230
Éditeur: the Royal Society of Chemistry
DOI: 10.1039/d1na00394a

Characterisation of observed heat transfer deterioration modes at supercritical pressure with the aid of a CFD model

Auteurs: A. Pucciarelli, S. Kassem, W. Ambrosini
Publié dans: Annals of Nuclear Energy, Numéro 178, 2023, Page(s) 109376, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2022.109376

A slow positron beam study of the oxidation behaviour of 310S stainless steel and alloy 800HT exposed to supercritical water

Auteurs: Jarmila Degmová, Yamin Song, Bingsheng Li, Stanislav Sojak, Xingzhong Cao, Radek Novotný, Michal Novák, Werner Egger, Vladimír Kršjak
Publié dans: The Journal of Supercritical Fluids, Numéro Volume 202, 2023, Page(s) 106057, ISSN 0896-8446
Éditeur: Elsevier BV
DOI: 10.1016/j.supflu.2023.106057

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Auteurs: Thomas Schulenberg, Ivan Otic
Publié dans: ASME J of Nuclear Rad Sci., 2022, ISSN 2332-8983
Éditeur: Journal of nuclear engineering and radiation science
DOI: 10.1115/1.4052191

CFD prediction of heat transfer at supercritical pressure with rough walls: Parametric analyses and comparison with experimental data

Auteurs: S. Kassem, A. Pucciarelli, W. Ambrosini
Publié dans: Annals of Nuclear Energy, Numéro 188, 2023, Page(s) 109815, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.109815

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

Auteurs: Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko
Publié dans: ASME J of Nuclear Rad Sci., 2022, ISSN 2332-8983
Éditeur: ASME
DOI: 10.1115/1.4052590

European Research Program on Supercritical Water-Cooled Reactor

Auteurs: M. Kryková, T. Schulenberg, M. Arnoult Růžičková, A. Sáez-Maderuelo, I. Otic, S. Czifrus, L. Cizelj, G. L. Pavel
Publié dans: Journal of Nuclear Engineering and Radiation Science, Numéro Apr 2021, Vol 7(2): 021301, 2021, Page(s) 5 pages, ISSN 2332-8983
Éditeur: ASME International
DOI: 10.1115/1.4048901

Neutronic calculations for preliminary core design of SCW-SMR

Auteurs: Csenge Antók, Szabolcs Czifrus, Valerio Giusti
Publié dans: Annals of Nuclear Energy, Numéro 209, 2024, Page(s) 110805, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2024.110805

Special Issue: Behavior of Materials (Alloys, Coatings) in Conditions Specific to Gen IV Nuclear Reactors

Auteurs: Manuela Fulger, Kittima Khumsa-Ang, Monika Šípová, Catalin Marian Ducu, Alberto Sáez-Maderuelo
Publié dans: Coatings, Numéro Coatings 2023, 13(1), 58, 2022, ISSN 2079-6412
Éditeur: MDPI
DOI: 10.3390/coatings13010058

Corrosion and Electrochemical Properties of Laser-Shock-Peening-Treated Stainless Steel AISI 304L inVVER Primary Water Environment

Auteurs: Xavier Arnoult, Mariana Arnoult-Ruzickova, Jan Manak, Alberto Viani, Jan Brajer, Michel Arrigoni, Radek Kolman, Jan Macák
Publié dans: Metals, 2022, ISSN 2075-4701
Éditeur: MDPI
DOI: 10.3390/met12101702

A study on the corrosion behaviour of stainless steel 08Cr18Ni10Ti in supercritical water

Auteurs: Monika Šípová, Daniela Marušáková, Claudia Aparicio, Jan Procházka, Patricie Halodová,
Publié dans: Corrosion Science, Numéro Volume 211, 2023, 110853, 2023, ISSN 0010-938X
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.corsci.2022.110853

The effect of chromium-based coatings on corrosion behavior of alloy Zr1Nb in 70ppm Li+ water environment

Auteurs: Michal Novák, Radek Novotný, Jaromír Valtr, David Dašek, Ladislav Cvrček, Jakub Krejčí, Věra Vrtílková, Jan Macák
Publié dans: Journal of Nuclear Materials, Numéro 599, 2025, Page(s) 155245, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2024.155245

Review of Euratom projects on design, safety assessment, R&D and licensing for ESNII/Gen-IV reactor systems

Auteurs: Mikityuk, Konstantin, Ferreira, Miguel, Hatala, Branislav, Kloosterman, J.L., Šípová, Monika
Publié dans: EPJ Nuclear Sciences and Technologies, Volume 9, 2023, Numéro Article number 18, 2023, ISSN 2491-9292
Éditeur: EPJ Nuclear sciences & technologies
DOI: 10.1051/epjn/2022048

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Auteurs: Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin
Publié dans: Journal of Nuclear Engineering and Radiation Science, Numéro 8, 2022, ISSN 2332-8983
Éditeur: ASME International
DOI: 10.1115/1.4052974

Progress on a Pre-Conceptual Supercritical Water-Cooled Small Modular Reactor

Auteurs: Armando Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto/D'Ansi Mendoza España, Jimmy Chow, Danila Roubtsov, Hygreeva Kiran Namburi
Publié dans: Journal of Nuclear Engineering and Radiation Science, 2025, Page(s) 1-58, ISSN 2332-8983
Éditeur: ASME International
DOI: 10.1115/1.4068326

Generation of synthetic FLAIR MRI image from real CT image for accurate synovial fluid segmentation in human knee image

Auteurs: Isam F. Abu-Qasmieh, Ihssan S. Masad, Hiam Alquran, Khaled Z. Alawneh
Publié dans: Neural Network World, Numéro 33, 2023, Page(s) 191-203, ISSN 2336-4335
Éditeur: Czech Technical University in Prague - Central Library
DOI: 10.14311/nnw.2023.33.012

A shape function approach for predicting deteriorated heat transfer to supercritical pressure fluids on account of a thermal entry length phenomenon

Auteurs: Andrea Pucciarelli, Walter Ambrosini
Publié dans: Nuclear Engineering and Design, Numéro 397, 2024, Page(s) 111923, ISSN 0029-5493
Éditeur: Elsevier BV
DOI: 10.1016/j.nucengdes.2022.111923

Euratom Research and Training in 2022: challenges, achievements and future perspectives

Auteurs: Roger Garbil, Seif Ben Hadj Hassine, Patrick Blaise, Cécile Ferry
Publié dans: EPJ Nuclear Sciences & Technologies, Numéro 10, 2024, Page(s) E1, ISSN 2491-9292
Éditeur: EDP Sciences
DOI: 10.1051/epjn/2024006

The effect of different surface treatments of 310S austenitic stainless steel on the corrosion behavior in supercritical water using slow positron methods

Auteurs: Yamin Song, Vladimir Krsjak, Vladimir Slugen, Radek Novotny, Stanislav Sojak, Michal Novak, Julius Dekan, Xingzhong Cao, Jarmila Degmova
Publié dans: Materials and Corrosion, Numéro 75, 2024, Page(s) 856-866, ISSN 0947-5117
Éditeur: Wiley Online Library
DOI: 10.1002/maco.202313999

Transfer matrix method for analysis of flow thermohydraulic characteristics with extremely nonlinear behavior of thermophysical properties using channel approach

Auteurs: Vladislav Filonov, Yuliia Filonova, Yaroslav Dubyk, Evgen Pis'mennyi
Publié dans: International Journal of Heat and Mass Transfer, Numéro 187, 2023, Page(s) 122531, ISSN 0017-9310
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.ijheatmasstransfer.2022.122531

Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction

Auteurs: K. Khumsa-Ang, S. Rousseau, O. Shiman
Publié dans: Journal of Nuclear Engineering and Radiation Science, Numéro 8, 2022, ISSN 2332-8983
Éditeur: Journal of Nuclear Engineering and Radiation Science
DOI: 10.1115/1.4052520

A study of the effect of pyramid roughness on turbulent heat transfer in supercritical water

Auteurs: Chinembiri, Kenneth; He, Shuisheng; Wang, Wei
Publié dans: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Page(s) 783-793, ISBN 9791256081332
Éditeur: Pisa University Press

Advances in the development of a fluid-to-fluid similarity theory for fluids at supercritical pressure: Results from sensitivity analyses

Auteurs: DE ANGELIS, ALESSANDRO PUCCIARELLI, ANDREA KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED AMBROSINI, WALTER
Publié dans: 2021 28th International Conference on Nuclear Engineering, ICONE 2021, 2021, ISBN 978-0-7918-8526-0
Éditeur: ASME
DOI: 10.1115/icone28-64713

DETERIORATED HEAT TRANSFER INFLUENCE ON THE STRESS-STRAIN STATE OF SMR SCWR FUEL BUNDLES

Auteurs: Yaroslav Dubyk Vladislav Filonov Olexandr Kovalenko Yuliia Filonova
Publié dans: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Éditeur: 10th International Symposium on SCWRs (ISSCWR-10)

Modelling of gravity-assited loop heat pipe experiments for pasive heat removal

Auteurs: A. McLellan, X. Huang, M. Gaudet and A. Nava-Dominguez
Publié dans: 2021
Éditeur: ISSCWR-10

DIFFERENTIAL METHOD FOR PREDICTING HEAT TRANSFER DETERIORATION REGIMES IN SUPERCRITICAL CHANNELS AND ROD ASSEMBLIES

Auteurs: Vladislav Filonov, Yuliia Filonova, Oleksandr Kovalenko, Dmitriy Fedorov
Publié dans: 2024
Éditeur: ICONE31

DETAILING OF EXISTING PROBE STUDIES OF DETERIORATED HEAT TRANSFER DURING UPWARD AND DOWNWARD FLOW USING QUASI-DNS

Auteurs: Vladislav Filonov, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Publié dans: 2025
Éditeur: ISSCWR-11

Current results of BME NTI in the ECC-SMART project: different analysis on the SCW-SMR

Auteurs: Tamás Varju, Attila Kiss, Csenge Antók, Boglárka Babcsány, Ildikó Boros, Péter Mészáros, Zeno Bertesina, Szabolcs Czifrus
Publié dans: Proceedings of the 2024 31st International Conference on Nuclear Engineering, ICONE31, August 4-8, 2024, Prague, Czech Republic, ICONE31-135760, 2024, Page(s) 1-10
Éditeur: American Society of Mechanical Engineers

ANALYSES OF IBSCTH TESTS USING SYSTEM AND CFD CODES

Auteurs: Guido Mazzini, Alis Ruscak Musa, Jakub Spacek, Walter Ambrosini, Andrea Pucciarelli, Sara Kassem
Publié dans: 2025
Éditeur: ISSCWR-11

Design concept of a super pressurized water reactor

Auteurs: Thomas Schulenberg, Szabolcs Czifruss
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 115-125, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

Effect of the Heat Transfer Correlation Choice on the Coupled Assessment of Energy Release and Stress-Strain State of an Elementary Supercritical Fuel Rod Under Nuclear Heating Conditions

Auteurs: Vladislav Filonov, Oleksandr Kovalenko, Yaroslav Dubyk, Yuliia Filonova, Dmitriy Fedorov
Publié dans: 2024
Éditeur: ICONE31

In-situ electrochemical corrosion testing of 310S steel in supercritical water

Auteurs: Petr Roztočil, David Dašek, Jaromír Valtr, Petr Čech, Mariana Arnoult-Růžičková, Michal Novák, Radek Novotný, Petr Sajdl, Jan Macák
Publié dans: 11th International symposium on supercritical water-cooled reactors : Pisa, Italy, February 3-5, 2025, 2025, Page(s) 407, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

Discussing CFD analysis of horizontal and vertical upward flow under supercritical conditions

Auteurs: Attila Kiss, Balázs Kiss
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 829-841, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

Generic results of the SCW-SMR pre-licensing study in the frame of ECC-SMART project

Auteurs: Andrej Prošek, Leon Cizelj, Ildikó Boros, Attila Kiss, Ivan Otić, Alberto Sáez-Maderuelo, Jiří Duspiva, Guido Mazzini, Monika Šípová, Gabriel Pavel, Oliver Martin, Radek Novotny, Yaroslav Dubyk
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 333-344, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

Prediction of heat transfer deterioration and recovery

Auteurs: Zewen Zou, Shuisheng He
Publié dans: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Page(s) P. 287-298
Éditeur: Pisa University Press

Differential Method for Predicting Heat Transfer Deterioration Regimes in Supercritical Channels and Rod Assemblies

Auteurs: Vladislav Filonov, Yuliia Filonova, Oleksandr Kovalenko, Dmitriy Fedorov
Publié dans: Proceeding of 2024 31st International Conference on Nuclear Engineering ICONE31, 2024, Page(s) 11 pages, ISBN 978-0-7918-8824-7
Éditeur: American Society of Mechanical Engineers

Customising a system code for the analysis of the thermal-hydraulic behaviour of a supercritical pressure light water small modular reactor

Auteurs: Omar Chaaraoui, Andrea Pucciarelli, Walter Ambrosini, Ivan Otic, Thomas Schulenberg, Chris Allison, Zheng Fu,
Publié dans: 2024
Éditeur: ICONE31

Effect of the Heat Transfer Correlation Choice on the Coupled Assessment of Energy Release and Stress-Strain State of an Elementary Supercritical Fuel Rod Under Nuclear Heating Conditions

Auteurs: Vladislav Filonov, Oleksandr Kovalenko, Yaroslav Dubyk, Yuliia Filonova, Dmitriy Fedorov
Publié dans: Proceeding of 2024 31st International Conference on Nuclear Engineering ICONE31, 2024, Page(s) 13 pages, ISBN 978-0-7918-8824-7
Éditeur: American Society of Mechanical Engineers

Modelling the influence of surface roughness on heat transfer at supercritical pressure

Auteurs: Kassem, Sara, Pucciarelli, Andrea, Ambrosini, Walter
Publié dans: 11th International symposium on supercritical water-cooled reactors : Pisa, Italy, February 3-5, 2025, 2025, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

Development Of Small Modular Reactor Cooled by Supercritical Water Within The ECC-SMART Project.

Auteurs: Monika Šípová, Alberto Saez-Maderuelo, Ivan Otic, Szabolcs Czifrus, Leon Cizelj
Publié dans: 2024
Éditeur: NENE2024

STUDY OF THE CORROSION BEHAVIOR IN SUPERCRITICAL WATER OF AN AUSTENITIC STAINLESS STEEL 316L MANUFACTURED BY COLD SPRAY

Auteurs: A. Saéz-Maderuelo, R. Novotny, M. Novak et al.
Publié dans: 2025
Éditeur: ISSCWR-11

EXTRAPOLATION OF HEAT TRANSFER DATA FOR CARBON DIOXIDE TO THE OPERATING CONDITIONS OF SCWR

Auteurs: PUCCIARELLI, ANDREA [Investigation] (Corresponding) AMBROSINI, WALTER [Supervision]
Publié dans: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium, March 6 - 11, 2022, 2022
Éditeur: NURETH-19

Safety systems required for a supercritical water-cooled reactor

Auteurs: Thomas Schulenberg
Publié dans: 2023
Éditeur: Workshop on Safety of Small and Modular Reactors

Implementation of the ECC-SMART: Joint European Canadian Chinese Development of Small Modular Reactor Technology

Auteurs: M. Krýdová, M. Šípová
Publié dans: 2025
Éditeur: ISSCWR-11

Transfer matrix method for analysis of thermohydraulic characteristics of supercritical water using sub-channel approach

Auteurs: V. Filonov, Y. Filonova, V.Razumovskiy, and Y. Dubyk
Publié dans: 2021
Éditeur: ISSCWR-10

On the Choice of Corresponding Pressures in a Novel Fluid-to-Fluid Similarity Theory for Heat Transfer at Supercritical Pressure

Auteurs: PUCCIARELLI, ANDREA [Conceptualization] (Corresponding) KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED [Investigation] AMBROSINI, WALTER [Supervision]
Publié dans: Proceedings of the International Conference Nuclear Energy for New Europe, 2021, ISBN 978-961-6207-51-5
Éditeur: Nuclear Society of Slovenia

Numerical Analysis of Turbulent Heat Transfer under Super-Critical Pressure Conditions

Auteurs: F. Wiltschko, I. Otic and X. Cheng
Publié dans: 2021
Éditeur: ISSCWR-10

Design concept of a super pressurized water reactor

Auteurs: Thomas Schulenberg, Szabolcs Czifrus
Publié dans: 2025
Éditeur: ISSCWR11

CONSIDERATIONS ABOUT CORRELATIONS FOR HEAT TRANSFER TO SUPERCRITICAL PRESSURE FLUIDS SPANNING ALL REGIMES

Auteurs: """KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED [Investigation] PUCCIARELLI, ANDREA [Investigation] (Corresponding) AMBROSINI, WALTER [Supervision]"""
Publié dans: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium, March 6 - 11, 2022, 2022
Éditeur: NURETH-19

Design and analysis of a reactor pressure vessel for the super pressurized water reactor

Auteurs: Álvaro Juan Fernández, Thomas Schulenberg
Publié dans: 2025
Éditeur: ISSCWR11

Assessment of Corrosion Behavior of Cladding Materials for SCW-SMR in Static Conditions: Results Obtained in ECC SMART Project

Auteurs: Manuela Fulger, Daniel Petrescu, Valentin Lautaru, Aurel David, Catalin Marian Ducu
Publié dans: 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, ISBN 979-12-5608-133-2
Éditeur: University of Pisa Press

Electrochemical impedance spectroscopy of steels in supercritical water

Auteurs: J.Macák, D.Dašek, J.Valtr, P.Roztočil, M.Arnoult-Růžičková, P.Sajdl, R.Novotný, M.Novák
Publié dans: 2023
Éditeur: EIA-13

Evaluation of Three-Dimensional Initial Dynamics of the Decompression Wave at Lb Loca in the Advanced Supercritical Reactor Ecc-Smart

Auteurs: Vladislav Filonov, Yaroslav Dubyk, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Publié dans: 2024
Éditeur: Proceedings

Prediction of heat transfer deterioration and recovery

Auteurs: Z Zou, S He
Publié dans: 2025
Éditeur: ISSCWR-11

A DNS Study on the Effect of Idealised Surface Roughness for Supercritical flows in Horizontal and Vertical Channels

Auteurs: K. Chinembiri, W. Wang, S. He
Publié dans: 2025
Éditeur: NURETH

Electrochemical Impedance Spectroscopy of Steels in Supercritical Water

Auteurs: Jan Macák, David Dašek, Jaromír Valtr, Petr Roztočil, Mariana Arnoult-Růžičková,Petr Sajdl, Radek Novotný, Michal Novák
Publié dans: 2025
Éditeur: 55th Heyrovsky Discussions

Az SM-SCWR koncepció Apros és CFD modellezése (in English: The Apros and CFD modelling of SM-SCWR concept)

Auteurs: Tamás Varju - Attila Kiss
Publié dans: 2022
Éditeur: XIX. MNT Nukleáris Technikai Szimpózium

OUTCOMES OF A SUCCESSFUL FLUID-TO-FLUID SIMILARITY THEORY FOR HEAT TRANSFER AT SUPERCRITICAL PRESSURES

Auteurs: KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED (Primo) [Investigation] (Corresponding) PUCCIARELLI, ANDREA (Secondo) [Conceptualization] AMBROSINI, WALTER (Ultimo) [Supervision]
Publié dans: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Éditeur: 10th International Symposium on SCWRs (ISSCWR-10)

Application of impedance spectroscopy for in-situ corrosion tests in supercritical water

Auteurs: J.Macák, P.Roztočil, J.Valtr, D.Dašek, M.Arnoult-Růžičková, P.Sajdl
Publié dans: 2023
Éditeur: IWIS-16

In-situ corrosion study of 800H alloy in supercritical water

Auteurs: Jaromír Valtr, Mariana Arnoult-Růžičková, Michal Novák1, Radek Novotný, Xavier Arnoult, Daniela Marušáková, Petr Sajdl, Jan Macák
Publié dans: 11th International symposium on supercritical water-cooled reactors : Pisa, Italy, February 3-5, 2025, 2025, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

New developments of sub-channel CFD for rod bundles with wire wrapped spacers

Auteurs: Chenxin Zhang, Bo Liu, Shuisheng He
Publié dans: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Page(s) 745-756
Éditeur: Pisa University Press

NEW UNDERSTANDING OF HEAT TRANSFER DETERIORATION DUE TO BUOYANCY

Auteurs: Zewen Zou, Jundi He, Elena Marensi, Shuisheng He
Publié dans: International Heat Transfer Conference Digital Library, 2023, 2023, Page(s) ID: 744, ISBN 978-1-56700-537-0
Éditeur: Begel House Inc.

Evaluation of Three-Dimensional Initial Dynamics of the Decompression Wave at LB LOCA in the Advanced Supercritical Reactor Ecc-Smart

Auteurs: Vladislav Filonov, Yaroslav Dubyk, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Publié dans: Proceeding of 2024 31st International Conference on Nuclear Engineering ICONE31, 2024, Page(s) 10 pages, ISBN 978-0-7918-8824-7
Éditeur: American Society of Mechanical Engineers

SM-SCWR zónatervezés és kapcsolt RELAP5 - Serpent2 számítások (in English: Core designing of SM-SCWR and coupled RELAP5 - Serpent2 calculations)

Auteurs: Szabolcs Czifrus - Péter Mészáros
Publié dans: 2022
Éditeur: XIX. MNT Nukleáris Technikai Szimpózium

CONSIDERATIONS ON A FLUID TO FLUID SCALING THEORY FOR HEAT TRANSFER TO SUPERCRITICAL FLUIDS: RECOMMENDATIONS FOR NON-UNIFORM HEAT FLUX CONDITIONS

Auteurs: PUCCIARELLI, ANDREA KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED AMBROSINI, WALTER
Publié dans: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Éditeur: ISSCWR-1

One dimensional analysis of heat transfer along corroded rods in vertical channels at supercritical pressure conditions

Auteurs: F. Wiltschko, I. Otic and J. Vitt
Publié dans: 2021
Éditeur: ENYGF 2021

Coupling of APROS and SPNDYN to analyse the SCW-SMR concept within ECC-SMART

Auteurs: Tamás Varju, Zeno Bertesina, Boglárka Babcsány
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 173-185, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

MATERIAL RESEARCH FOR SMALL MODULAR REACTOR COOLED BY SUPERCRITICAL WATER – ECC-SMART

Auteurs: MARUŠÁKOVÁ Daniela, ŠÍPOVÁ Monika
Publié dans: Proceedings 31st International Conference on Metallurgy and Materials, 2022, Page(s) 419-425, ISBN 978-80-88365-06-8
Éditeur: METAL 2022
DOI: 10.37904/metal.2022.4480

Modelling the influence of surface roughness on heat transfer at supercritical pressure

Auteurs: Sara Kassem, Andrea Pucciarelli, Walter Ambrosini,
Publié dans: 2025
Éditeur: ISSCWR-11

Suggestion for Design of a Small Modular SCWR

Auteurs: T. Schulenberg and I. Otic
Publié dans: 2021
Éditeur: ISSCWR-10

Oxidation behaviour of Fe-Cr-Ni alloys in static conditions in supercritical water

Auteurs: Manuela Fulger, Maria Mihalache, Daniel Petrescu
Publié dans: 2021
Éditeur: ISSCWR 10

Hybrid finite element SPN analysis of an SCW-SMR concept within the ECC-SMART project

Auteurs: Gergely Illés, Boglárka Babcsány
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 187-198, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

ELECTROCHEMICAL APPROACH: COULD IT ASSIST IN MATERIAL – SUPERCRITICAL WATER INTERACTION STUDIES?

Auteurs: J. Macák, R. Novotný, P. Sajdl, M. Arnoult-Růžičková
Publié dans: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Éditeur: Research Centre Rez, CR

Specifications of a Gen-IV SCWR-FQT Reactor Physics Computational Benchmark

Auteurs: J. Chow, S. Kelly, A. Nava-Dominguez and D. Roubtsov
Publié dans: 2021
Éditeur: ISSCWR-10

New developments of sub-channel CFD for rod bundles with wire wrapped spacers

Auteurs: C Zhang, B Liu, S He
Publié dans: 2025
Éditeur: ISSCWR-11

RESULTS FROM CORROSION TESTS PERFORMED IN ECC-SMART PROJECT

Auteurs: Alberto Sáez-Maderuelo, Manuela Fulger, Aki Toivonen, Radek Novotny, Jan Macak, Kittima Khumsa-Ang, Daniela Marušáková, Lefu Zhang, Zhangjian Zhou,Jarmila Degmová
Publié dans: 2024
Éditeur: EUROCORR 2024

ANALYSIS OF ROUGHNESS EFFECTS ON TURBULENT HEAT TRANSFER TO SUPERCRITICAL WATER IN A HORIZONTAL TUBE

Auteurs: Yuhao Xu, Jivan Khatry, Ivan Otic and Jie Zhu
Publié dans: 2025
Éditeur: The University of Pisa and the Dipartimento di Ingegneria Civile e Industriale

Numerical Simulation of Supercritical Water Flow in a Wall-Heated Horizontal Test Section

Auteurs: Jivan Khatry, Yikai Liu, and Jie Zhu
Publié dans: 2024
Éditeur: the Canadian Nuclear Society (CNS), and the Korean Nuclear Society (KNS)

Electrochemical Impedance Measurements in Supercritical Water

Auteurs: P.Roztočil, D.Dašek, M.Novák, R.Novotný, M.Arnoult-Růžičková, P.Sajdl, J.Macák
Publié dans: 2022
Éditeur: 17th ECG-COMON Meeting

Comparative Analysis of Energy Deposition Modes Available in Serpent 2 Within the Framework of the SCWR-FQT Reactor Physics Benchmark

Auteurs: Boglárka Babcsány (Budapest Univ. Technology and Economics), Valerio Giusti (University of Pisa), Andreea Moise (Institute for Nuclear Research), Jimmy C. Chow (Canadian Nuclear Laboratories)
Publié dans: International Conference on Physics of Reactors 2022 (PHYSOR 2022), Numéro PHYSOR 2022, 2022
Éditeur: PHYSOR 2022

Stress Corrosion Cracking Behavior of Stainless Steel 310S in Supercritical Water

Auteurs: Marušáková, D.; Šípová, M.; Novák, M.; Novotný, R.
Publié dans: 2024
Éditeur: NENE2023

ASSESSMENT OF THE FAILURE TIME OF THE ECC-SMART SUPERCRITICAL REACTOR VESSEL IN THE LATE PHASE OF A SEVERE ACCIDENT

Auteurs: Vladislav Filonov, Dmitriy Fedorov, Olexander Kovalenko, Yaroslav Dubyk, Yuliia Filonova
Publié dans: 2025
Éditeur: ISSCWR11

EVALUATION OF LONG-TERM EXPOSURE OF 310S AND 800H UNDER CONDITIONS OF SCW-SMR

Auteurs: Daniela Marušáková, Jan Vít, Monika Šípová
Publié dans: 2025
Éditeur: ISSCWR-11

MULTIPHYSICS ASSESSMENT OF THE SCW SMR HEAT GENERATING CHANNEL CONDITION USING DIFFERENTIAL METHOD OF THE HEAT TRANSFER INTENSITY AND RESISTANCE CALCULATION

Auteurs: Vladislav Filonov, Olexander Kovalenko, Dmitriy Fedorov, Yuliia Filonova
Publié dans: 2025
Éditeur: ISSCWR11

Comparison of CFD analysis results of horizontal flow in SCW-SMR fuel assembly with and without wrapped wire spacers

Auteurs: Attila Kiss, László Adorján
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 843-853, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

MULTIPHYSICS ASSESSMENT OF THE SCW SMR HEAT GENERATING CHANNEL CONDITION USING DIFFERENTIAL METHOD OF THE HEAT TRANSFER INTENSITY AND RESISTANCE CALCULATION

Auteurs: Vladislav Filonov, Olexander Kovalenko, Dmitriy Fedorov, Yuliia Filonova
Publié dans: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Page(s) 199-218, ISBN 9791256081332
Éditeur: Pisa University Press

STUDY OF THE EFFECT OF NEUTRON IRRADIATION ON THE MECHANICAL AND CORROSION BEHAVIOUR OF CANDIDATE MATERIALS FOR SCW-SMR

Auteurs: Monika Šípová, Jitka Klaisnerová, Daniela Marušáková, Jan Vít
Publié dans: 2025
Éditeur: ISSCWR-11

TREATMENT AND EVALUATION OF SURFACE ROUGHNESS OF FUEL CLADDING TO MITIGATE THE DETEORIATED HEAT TRANSFER IN SCW–SMR CONCEPT

Auteurs: Jan Vít, Monika Šípová, D. Bricin
Publié dans: 2025
Éditeur: ISSCWR-11

TRANSFER MATRIX METHOD FOR ANALYSIS OF THERMOHYDRAULICCHARACTERISTICS OF SUPERCRITICAL WATER USING CHANNEL APPROACH

Auteurs: Vladislav Filonov Yuliia Filonova Yaroslav Dubyk V. Razumovskiy
Publié dans: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Éditeur: 10th International Symposium on SCWRs (ISSCWR-10)

CFD modeling and validation of supercritical fluid heat transfer along rough wall surfaces

Auteurs: H. Li, H. Anglart
Publié dans: 2025
Éditeur: ISSCWR-11

Considerations on current methodologies for the assessment of engineering correlations for heat transfer at supercritical pressures

Auteurs: Sara Kassem, Andrea Pucciarelli, Walter Ambrosini
Publié dans: 2024
Éditeur: ICONE31

ASSESSMENT OF THE FAILURE TIME OF THE ECC-SMART SUPERCRITICAL REACTOR VESSEL IN THE LATE PHASE OF A SEVERE ACCIDENT

Auteurs: Vladislav Filonov, Dmitriy Fedorov, Olexander Kovalenko, Yaroslav Dubyk, Yuliia Filonova
Publié dans: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Page(s) 313-332, ISBN 9791256081332
Éditeur: Pisa University Press

EXTENDING A FLUID-TO-FLUID SIMILARITY RATIONALE FOR HEAT TRANSFER AT SUPERCRITICAL PRESSURE TO R134a

Auteurs: KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED PUCCIARELLI, ANDREA AMBROSINI, WALTER
Publié dans: 2021 28th International Conference on Nuclear Engineering, ICONE 2021, Virtual, Online, 2021
Éditeur: ASME
DOI: 10.1115/icone28-64822

A study of the effect of pyramid roughness on turbulent heat transfer in supercritical water

Auteurs: Kenneth Chinembiri, Shuisheng He, Wei Wang
Publié dans: 2025
Éditeur: ISSCWR-11

PEFFECT OF EXPOSURE TO SUPERCRITICAL WATER ON CORROSION BEHAVIOUR OF SELECTED MATERIALS

Auteurs: ŠÍPOVÁ Monika, MARUŠÁKOVÁ Daniela, PROCHÁZKA Jan
Publié dans: Proceedings 31st International Conference on Metallurgy and Materials, Numéro 31st International Conference on Metallurgy and Materials, Orea Congress Hotel Brno, Czech Republic, EU, May 18 - 19, 2022, 2022, Page(s) 426-430, ISBN 978-80-88365-06-8
Éditeur: Metal 2022
DOI: 10.37904/metal.2022.4477

Turbulent Heat Transfer in a Supercritical Downward Flow

Auteurs: K. Chinembiri & S. He
Publié dans: 2022
Éditeur: HEFAT 2022

CFD modeling and validation of supercritical fluid heat transfer along rough wall surfaces

Auteurs: Haipeng Li, Henryk Anglart
Publié dans: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Page(s) 795-806, ISBN 979-12-5608-133-2
Éditeur: Pisa University Press

Study of corrosion behaviour of Fe-Cr-Ni alloys in supercritical water using in-situ electrochemical techniques

Auteurs: Viachaslau Radzeuski
Publié dans: 2024
Éditeur: BSc thesis

Study of corrosion behaviour of Fe-Cr-Ni alloys in supercritical water using in-situ electrochemical techniques

Auteurs: Viachaslau Radzeuski
Publié dans: BSc degree thesis, 2024
Éditeur: University of chemistry and technology, Prague

Thermal-hydraulic analyses in support to the development of an innovative reactor concept at supercritical pressure

Auteurs: Candidate: Omar Chaaraoui Tutors: Walter Ambrosini, Andrea Pucciarelli
Publié dans: 2024
Éditeur: Università di Pisa

Study of corrosion kinetics of alloy 800H in supercritical water: correlation of gravimetric and electrochemical data

Auteurs: Eva Bažantová
Publié dans: MSc degree thesis, 2024
Éditeur: University of chemistry and technology, Prague

Study of corrosion of materials in supercritical water conditions for the Generation IV nuclear reactor concept SCWR

Auteurs: Petr Roztočil
Publié dans: MSc degree thesis, 2022
Éditeur: University of chemistry and technology, Prague

Design of a reactivity control system of a supercritical water cooled small modular reactor

Auteurs: Norbert Krisztián Tóth
Publié dans: MSc thesis of energy engineering MSc student, 2023, Page(s) 1-83
Éditeur: Institute of Nuclear Techniques, Budapest University of Technology and Economics

A comprehensive study of corrosion and stress corrosion cracking of 310S austenitic steel as a candidate fuel cladding for a SMR-SCW

Auteurs: Daniela Marušáková
Publié dans: 2024
Éditeur: PhD thesis

Study of corrosion kinetics of alloy 800H in supercritical water: correlation of gravimetric and electrochemical data

Auteurs: Eva Bažantová
Publié dans: 2024
Éditeur: BSc thesis

CFD analysis of the horizontal flow of water under supercritical pressure in SCW-SMR relevant geometries

Auteurs: Balázs Kiss
Publié dans: MSc thesis of energy engineering MSc student, 2024, Page(s) 1-68
Éditeur: Institute of Nuclear Techniques, Budapest University of Technology and Economics

ANALYSIS OF HEAT TRANSFER PHENOMENA AT SUPERCRITICAL PRESSURE SUPPORTED BY A FLUID-TO-FLUID SIMILARITY THEORY

Auteurs: Candidate: Sara Kassem Tutors: Walter Ambrosini, Andrea Pucciarelli
Publié dans: 2024
Éditeur: Università di Pisa

Corrosion testing in supercritical water

Auteurs: Petr Čech
Publié dans: BSc degree thesis, 2022, Page(s) 31
Éditeur: University of chemistry and technology, Prague

Study of corrosion behaviour of 310S-AFA stainless steel in supercritical water

Auteurs: Petr Čech
Publié dans: 2024
Éditeur: MSc thesis

Investigation of corrosion behaviour of stainless steel 310S-AFA (Alumina Forming Austenitic) in supercritical water

Auteurs: Petr Čech
Publié dans: MSc degree thesis, 2024
Éditeur: University of chemistry and technology

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