Joint European Canadian Chinese development of Small Modular Reactor Technology

CORDIS proporciona enlaces a los documentos públicos y las publicaciones de los proyectos de los programas marco HORIZONTE.

Los enlaces a los documentos y las publicaciones de los proyectos del Séptimo Programa Marco, así como los enlaces a algunos tipos de resultados específicos, como conjuntos de datos y «software», se obtienen dinámicamente de OpenAIRE .

Resultado final

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.

Publicaciones

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

Autores: Tamás Varju, Boglárka Babcsány, Péter Mészáros, Csenge Antók, Szabolcs Czifrus
Publicado en: Annals of Nuclear Energy, 2025, Página(s) 111222, ISSN 0306-4549
Editor: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2025.111222

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

Autores: 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
Publicado en: The Journal of Supercritical Fluids, Edición 204, 2023, Página(s) 106091, ISSN 0896-8446
Editor: Elsevier BV
DOI: 10.1016/j.supflu.2023.106091

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

Autores: T. Varju, A. Csige, A. Kiss, V. Filonov, Y. Filonova, D. Fedorov, A. Pucciarelli, S. Kassem, W. Ambrosini
Publicado en: Nuclear Engineering and Design, Edición 421, 2024, Página(s) 113085, ISSN 0029-5493
Editor: 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

Autores: Kittima Khumsa-Ang, Alberto Mendoza, Armando Nava-Dominguez, Chukwudi Azih, Hussam Zahlan
Publicado en: Coatings, Edición 13, 2023, Página(s) 1648, ISSN 2079-6412
Editor: MDPI AG
DOI: 10.3390/coatings13091648

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

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

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

Autores: Boglárka Babcsány, Valerio Giusti, Andreea Moise, Péter Mészáros, Szabolcs Czifrus, Jimmy C. Chow
Publicado en: Annals of Nuclear Energy, Edición Volume 191, October 2023, 109903, 2023, Página(s) 19, ISSN 1873-2100
Editor: Elsevier Ltd.
DOI: 10.1016/j.anucene.2023.109903

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

Autores: Haodong Jia, Yingjie Wang, You Wang, Lu Han, Yujuan Zhang, Zhangjian Zhou
Publicado en: Materials, Edición 16, 2025, Página(s) 3497, ISSN 1996-1944
Editor: 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

Autores: Tamás Varju, Csenge Antók, Péter Mészáros, Boglárka Babcsány
Publicado en: Annals of Nuclear Energy, 2025, Página(s) 111221, ISSN 0306-4549
Editor: 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

Autores: Vladimir Slugen, Jarmila Degmova, Stanislav Sojak, Martin Petriska, Pavol Noga and Vladimir Krsjak
Publicado en: Metals, 2021, ISSN 2075-4701
Editor: MDPI
DOI: 10.3390/met11111689

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

Autores: K. Khumsa-Ang, M. Edwards, S. Rousseau
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 6, 2020, ISSN 2332-8983
Editor: 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

Autores: Vladimir Krsjak, Petr Hruska, Jarmila Degmova, Stanislav Sojak, Pavol Noga, Tielong Shen, Veronika Sabelova, Werner Eggere and Vladimir Slugen
Publicado en: Nanoscale Advances, 2021, ISSN 2516-0230
Editor: 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

Autores: A. Pucciarelli, S. Kassem, W. Ambrosini
Publicado en: Annals of Nuclear Energy, Edición 178, 2023, Página(s) 109376, ISSN 0306-4549
Editor: 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

Autores: Jarmila Degmová, Yamin Song, Bingsheng Li, Stanislav Sojak, Xingzhong Cao, Radek Novotný, Michal Novák, Werner Egger, Vladimír Kršjak
Publicado en: The Journal of Supercritical Fluids, Edición Volume 202, 2023, Página(s) 106057, ISSN 0896-8446
Editor: Elsevier BV
DOI: 10.1016/j.supflu.2023.106057

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Autores: Thomas Schulenberg, Ivan Otic
Publicado en: ASME J of Nuclear Rad Sci., 2022, ISSN 2332-8983
Editor: 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

Autores: S. Kassem, A. Pucciarelli, W. Ambrosini
Publicado en: Annals of Nuclear Energy, Edición 188, 2023, Página(s) 109815, ISSN 0306-4549
Editor: 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

Autores: Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko
Publicado en: ASME J of Nuclear Rad Sci., 2022, ISSN 2332-8983
Editor: ASME
DOI: 10.1115/1.4052590

European Research Program on Supercritical Water-Cooled Reactor

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

Neutronic calculations for preliminary core design of SCW-SMR

Autores: Csenge Antók, Szabolcs Czifrus, Valerio Giusti
Publicado en: Annals of Nuclear Energy, Edición 209, 2024, Página(s) 110805, ISSN 0306-4549
Editor: 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

Autores: Manuela Fulger, Kittima Khumsa-Ang, Monika Šípová, Catalin Marian Ducu, Alberto Sáez-Maderuelo
Publicado en: Coatings, Edición Coatings 2023, 13(1), 58, 2022, ISSN 2079-6412
Editor: MDPI
DOI: 10.3390/coatings13010058

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

Autores: Xavier Arnoult, Mariana Arnoult-Ruzickova, Jan Manak, Alberto Viani, Jan Brajer, Michel Arrigoni, Radek Kolman, Jan Macák
Publicado en: Metals, 2022, ISSN 2075-4701
Editor: MDPI
DOI: 10.3390/met12101702

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

Autores: Monika Šípová, Daniela Marušáková, Claudia Aparicio, Jan Procházka, Patricie Halodová,
Publicado en: Corrosion Science, Edición Volume 211, 2023, 110853, 2023, ISSN 0010-938X
Editor: 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

Autores: Michal Novák, Radek Novotný, Jaromír Valtr, David Dašek, Ladislav Cvrček, Jakub Krejčí, Věra Vrtílková, Jan Macák
Publicado en: Journal of Nuclear Materials, Edición 599, 2025, Página(s) 155245, ISSN 0022-3115
Editor: 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

Autores: Mikityuk, Konstantin, Ferreira, Miguel, Hatala, Branislav, Kloosterman, J.L., Šípová, Monika
Publicado en: EPJ Nuclear Sciences and Technologies, Volume 9, 2023, Edición Article number 18, 2023, ISSN 2491-9292
Editor: EPJ Nuclear sciences & technologies
DOI: 10.1051/epjn/2022048

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Autores: Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8, 2022, ISSN 2332-8983
Editor: ASME International
DOI: 10.1115/1.4052974

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

Autores: Armando Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto/D'Ansi Mendoza España, Jimmy Chow, Danila Roubtsov, Hygreeva Kiran Namburi
Publicado en: Journal of Nuclear Engineering and Radiation Science, 2025, Página(s) 1-58, ISSN 2332-8983
Editor: 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

Autores: Isam F. Abu-Qasmieh, Ihssan S. Masad, Hiam Alquran, Khaled Z. Alawneh
Publicado en: Neural Network World, Edición 33, 2023, Página(s) 191-203, ISSN 2336-4335
Editor: 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

Autores: Andrea Pucciarelli, Walter Ambrosini
Publicado en: Nuclear Engineering and Design, Edición 397, 2024, Página(s) 111923, ISSN 0029-5493
Editor: Elsevier BV
DOI: 10.1016/j.nucengdes.2022.111923

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

Autores: Roger Garbil, Seif Ben Hadj Hassine, Patrick Blaise, Cécile Ferry
Publicado en: EPJ Nuclear Sciences & Technologies, Edición 10, 2024, Página(s) E1, ISSN 2491-9292
Editor: 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

Autores: Yamin Song, Vladimir Krsjak, Vladimir Slugen, Radek Novotny, Stanislav Sojak, Michal Novak, Julius Dekan, Xingzhong Cao, Jarmila Degmova
Publicado en: Materials and Corrosion, Edición 75, 2024, Página(s) 856-866, ISSN 0947-5117
Editor: 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

Autores: Vladislav Filonov, Yuliia Filonova, Yaroslav Dubyk, Evgen Pis'mennyi
Publicado en: International Journal of Heat and Mass Transfer, Edición 187, 2023, Página(s) 122531, ISSN 0017-9310
Editor: 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

Autores: K. Khumsa-Ang, S. Rousseau, O. Shiman
Publicado en: Journal of Nuclear Engineering and Radiation Science, Edición 8, 2022, ISSN 2332-8983
Editor: 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

Autores: Chinembiri, Kenneth; He, Shuisheng; Wang, Wei
Publicado en: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Página(s) 783-793, ISBN 9791256081332
Editor: Pisa University Press

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

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

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

Autores: Yaroslav Dubyk Vladislav Filonov Olexandr Kovalenko Yuliia Filonova
Publicado en: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Editor: 10th International Symposium on SCWRs (ISSCWR-10)

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

Autores: A. McLellan, X. Huang, M. Gaudet and A. Nava-Dominguez
Publicado en: 2021
Editor: ISSCWR-10

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

Autores: Vladislav Filonov, Yuliia Filonova, Oleksandr Kovalenko, Dmitriy Fedorov
Publicado en: 2024
Editor: ICONE31

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

Autores: Vladislav Filonov, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Publicado en: 2025
Editor: ISSCWR-11

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

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

ANALYSES OF IBSCTH TESTS USING SYSTEM AND CFD CODES

Autores: Guido Mazzini, Alis Ruscak Musa, Jakub Spacek, Walter Ambrosini, Andrea Pucciarelli, Sara Kassem
Publicado en: 2025
Editor: ISSCWR-11

Design concept of a super pressurized water reactor

Autores: Thomas Schulenberg, Szabolcs Czifruss
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 115-125, ISBN 979-12-5608-133-2
Editor: 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

Autores: Vladislav Filonov, Oleksandr Kovalenko, Yaroslav Dubyk, Yuliia Filonova, Dmitriy Fedorov
Publicado en: 2024
Editor: ICONE31

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

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

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

Autores: Attila Kiss, Balázs Kiss
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 829-841, ISBN 979-12-5608-133-2
Editor: Pisa University Press

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

Autores: 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
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 333-344, ISBN 979-12-5608-133-2
Editor: Pisa University Press

Prediction of heat transfer deterioration and recovery

Autores: Zewen Zou, Shuisheng He
Publicado en: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Página(s) P. 287-298
Editor: Pisa University Press

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

Autores: Vladislav Filonov, Yuliia Filonova, Oleksandr Kovalenko, Dmitriy Fedorov
Publicado en: Proceeding of 2024 31st International Conference on Nuclear Engineering ICONE31, 2024, Página(s) 11 pages, ISBN 978-0-7918-8824-7
Editor: 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

Autores: Omar Chaaraoui, Andrea Pucciarelli, Walter Ambrosini, Ivan Otic, Thomas Schulenberg, Chris Allison, Zheng Fu,
Publicado en: 2024
Editor: 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

Autores: Vladislav Filonov, Oleksandr Kovalenko, Yaroslav Dubyk, Yuliia Filonova, Dmitriy Fedorov
Publicado en: Proceeding of 2024 31st International Conference on Nuclear Engineering ICONE31, 2024, Página(s) 13 pages, ISBN 978-0-7918-8824-7
Editor: American Society of Mechanical Engineers

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

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

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

Autores: Monika Šípová, Alberto Saez-Maderuelo, Ivan Otic, Szabolcs Czifrus, Leon Cizelj
Publicado en: 2024
Editor: NENE2024

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

Autores: A. Saéz-Maderuelo, R. Novotny, M. Novak et al.
Publicado en: 2025
Editor: ISSCWR-11

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

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

Safety systems required for a supercritical water-cooled reactor

Autores: Thomas Schulenberg
Publicado en: 2023
Editor: Workshop on Safety of Small and Modular Reactors

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

Autores: M. Krýdová, M. Šípová
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: V. Filonov, Y. Filonova, V.Razumovskiy, and Y. Dubyk
Publicado en: 2021
Editor: ISSCWR-10

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

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

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

Autores: F. Wiltschko, I. Otic and X. Cheng
Publicado en: 2021
Editor: ISSCWR-10

Design concept of a super pressurized water reactor

Autores: Thomas Schulenberg, Szabolcs Czifrus
Publicado en: 2025
Editor: ISSCWR11

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

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

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

Autores: Álvaro Juan Fernández, Thomas Schulenberg
Publicado en: 2025
Editor: ISSCWR11

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

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

Electrochemical impedance spectroscopy of steels in supercritical water

Autores: J.Macák, D.Dašek, J.Valtr, P.Roztočil, M.Arnoult-Růžičková, P.Sajdl, R.Novotný, M.Novák
Publicado en: 2023
Editor: EIA-13

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

Autores: Vladislav Filonov, Yaroslav Dubyk, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Publicado en: 2024
Editor: Proceedings

Prediction of heat transfer deterioration and recovery

Autores: Z Zou, S He
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: K. Chinembiri, W. Wang, S. He
Publicado en: 2025
Editor: NURETH

Electrochemical Impedance Spectroscopy of Steels in Supercritical Water

Autores: Jan Macák, David Dašek, Jaromír Valtr, Petr Roztočil, Mariana Arnoult-Růžičková,Petr Sajdl, Radek Novotný, Michal Novák
Publicado en: 2025
Editor: 55th Heyrovsky Discussions

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

Autores: Tamás Varju - Attila Kiss
Publicado en: 2022
Editor: XIX. MNT Nukleáris Technikai Szimpózium

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

Autores: KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED (Primo) [Investigation] (Corresponding) PUCCIARELLI, ANDREA (Secondo) [Conceptualization] AMBROSINI, WALTER (Ultimo) [Supervision]
Publicado en: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Editor: 10th International Symposium on SCWRs (ISSCWR-10)

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

Autores: J.Macák, P.Roztočil, J.Valtr, D.Dašek, M.Arnoult-Růžičková, P.Sajdl
Publicado en: 2023
Editor: IWIS-16

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

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

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

Autores: Chenxin Zhang, Bo Liu, Shuisheng He
Publicado en: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Página(s) 745-756
Editor: Pisa University Press

NEW UNDERSTANDING OF HEAT TRANSFER DETERIORATION DUE TO BUOYANCY

Autores: Zewen Zou, Jundi He, Elena Marensi, Shuisheng He
Publicado en: International Heat Transfer Conference Digital Library, 2023, 2023, Página(s) ID: 744, ISBN 978-1-56700-537-0
Editor: Begel House Inc.

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

Autores: Vladislav Filonov, Yaroslav Dubyk, Oleksandr Kovalenko, Yuliia Filonova, Dmitriy Fedorov
Publicado en: Proceeding of 2024 31st International Conference on Nuclear Engineering ICONE31, 2024, Página(s) 10 pages, ISBN 978-0-7918-8824-7
Editor: 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)

Autores: Szabolcs Czifrus - Péter Mészáros
Publicado en: 2022
Editor: 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

Autores: PUCCIARELLI, ANDREA KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED AMBROSINI, WALTER
Publicado en: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Editor: ISSCWR-1

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

Autores: F. Wiltschko, I. Otic and J. Vitt
Publicado en: 2021
Editor: ENYGF 2021

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

Autores: Tamás Varju, Zeno Bertesina, Boglárka Babcsány
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 173-185, ISBN 979-12-5608-133-2
Editor: Pisa University Press

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

Autores: MARUŠÁKOVÁ Daniela, ŠÍPOVÁ Monika
Publicado en: Proceedings 31st International Conference on Metallurgy and Materials, 2022, Página(s) 419-425, ISBN 978-80-88365-06-8
Editor: METAL 2022
DOI: 10.37904/metal.2022.4480

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

Autores: Sara Kassem, Andrea Pucciarelli, Walter Ambrosini,
Publicado en: 2025
Editor: ISSCWR-11

Suggestion for Design of a Small Modular SCWR

Autores: T. Schulenberg and I. Otic
Publicado en: 2021
Editor: ISSCWR-10

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

Autores: Manuela Fulger, Maria Mihalache, Daniel Petrescu
Publicado en: 2021
Editor: ISSCWR 10

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

Autores: Gergely Illés, Boglárka Babcsány
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 187-198, ISBN 979-12-5608-133-2
Editor: Pisa University Press

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

Autores: J. Macák, R. Novotný, P. Sajdl, M. Arnoult-Růžičková
Publicado en: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Editor: Research Centre Rez, CR

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

Autores: J. Chow, S. Kelly, A. Nava-Dominguez and D. Roubtsov
Publicado en: 2021
Editor: ISSCWR-10

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

Autores: C Zhang, B Liu, S He
Publicado en: 2025
Editor: ISSCWR-11

RESULTS FROM CORROSION TESTS PERFORMED IN ECC-SMART PROJECT

Autores: Alberto Sáez-Maderuelo, Manuela Fulger, Aki Toivonen, Radek Novotny, Jan Macak, Kittima Khumsa-Ang, Daniela Marušáková, Lefu Zhang, Zhangjian Zhou,Jarmila Degmová
Publicado en: 2024
Editor: EUROCORR 2024

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

Autores: Yuhao Xu, Jivan Khatry, Ivan Otic and Jie Zhu
Publicado en: 2025
Editor: 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

Autores: Jivan Khatry, Yikai Liu, and Jie Zhu
Publicado en: 2024
Editor: the Canadian Nuclear Society (CNS), and the Korean Nuclear Society (KNS)

Electrochemical Impedance Measurements in Supercritical Water

Autores: P.Roztočil, D.Dašek, M.Novák, R.Novotný, M.Arnoult-Růžičková, P.Sajdl, J.Macák
Publicado en: 2022
Editor: 17th ECG-COMON Meeting

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

Autores: Boglárka Babcsány (Budapest Univ. Technology and Economics), Valerio Giusti (University of Pisa), Andreea Moise (Institute for Nuclear Research), Jimmy C. Chow (Canadian Nuclear Laboratories)
Publicado en: International Conference on Physics of Reactors 2022 (PHYSOR 2022), Edición PHYSOR 2022, 2022
Editor: PHYSOR 2022

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

Autores: Marušáková, D.; Šípová, M.; Novák, M.; Novotný, R.
Publicado en: 2024
Editor: NENE2023

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

Autores: Vladislav Filonov, Dmitriy Fedorov, Olexander Kovalenko, Yaroslav Dubyk, Yuliia Filonova
Publicado en: 2025
Editor: ISSCWR11

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

Autores: Daniela Marušáková, Jan Vít, Monika Šípová
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: Vladislav Filonov, Olexander Kovalenko, Dmitriy Fedorov, Yuliia Filonova
Publicado en: 2025
Editor: ISSCWR11

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

Autores: Attila Kiss, László Adorján
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 843-853, ISBN 979-12-5608-133-2
Editor: Pisa University Press

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

Autores: Vladislav Filonov, Olexander Kovalenko, Dmitriy Fedorov, Yuliia Filonova
Publicado en: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Página(s) 199-218, ISBN 9791256081332
Editor: Pisa University Press

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

Autores: Monika Šípová, Jitka Klaisnerová, Daniela Marušáková, Jan Vít
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: Jan Vít, Monika Šípová, D. Bricin
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: Vladislav Filonov Yuliia Filonova Yaroslav Dubyk V. Razumovskiy
Publicado en: 10th International Symposium on SCWRs (ISSCWR-10), 2021
Editor: 10th International Symposium on SCWRs (ISSCWR-10)

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

Autores: H. Li, H. Anglart
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: Sara Kassem, Andrea Pucciarelli, Walter Ambrosini
Publicado en: 2024
Editor: ICONE31

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

Autores: Vladislav Filonov, Dmitriy Fedorov, Olexander Kovalenko, Yaroslav Dubyk, Yuliia Filonova
Publicado en: 11th International symposium on supercritical water-cooled reactors: Pisa, Italy, February 3-5, 2025, 2025, Página(s) 313-332, ISBN 9791256081332
Editor: Pisa University Press

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

Autores: KASSEM, SARA IBRAHIM ABDELSALAM MOHAMED PUCCIARELLI, ANDREA AMBROSINI, WALTER
Publicado en: 2021 28th International Conference on Nuclear Engineering, ICONE 2021, Virtual, Online, 2021
Editor: ASME
DOI: 10.1115/icone28-64822

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

Autores: Kenneth Chinembiri, Shuisheng He, Wei Wang
Publicado en: 2025
Editor: ISSCWR-11

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

Autores: ŠÍPOVÁ Monika, MARUŠÁKOVÁ Daniela, PROCHÁZKA Jan
Publicado en: Proceedings 31st International Conference on Metallurgy and Materials, Edición 31st International Conference on Metallurgy and Materials, Orea Congress Hotel Brno, Czech Republic, EU, May 18 - 19, 2022, 2022, Página(s) 426-430, ISBN 978-80-88365-06-8
Editor: Metal 2022
DOI: 10.37904/metal.2022.4477

Turbulent Heat Transfer in a Supercritical Downward Flow

Autores: K. Chinembiri & S. He
Publicado en: 2022
Editor: HEFAT 2022

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

Autores: Haipeng Li, Henryk Anglart
Publicado en: Proceedings of 11th International Symposium on Supercritical Water-Cooled Reactors, 2025, Página(s) 795-806, ISBN 979-12-5608-133-2
Editor: Pisa University Press

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

Autores: Viachaslau Radzeuski
Publicado en: 2024
Editor: BSc thesis

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

Autores: Viachaslau Radzeuski
Publicado en: BSc degree thesis, 2024
Editor: University of chemistry and technology, Prague

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

Autores: Candidate: Omar Chaaraoui Tutors: Walter Ambrosini, Andrea Pucciarelli
Publicado en: 2024
Editor: Università di Pisa

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

Autores: Eva Bažantová
Publicado en: MSc degree thesis, 2024
Editor: University of chemistry and technology, Prague

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

Autores: Petr Roztočil
Publicado en: MSc degree thesis, 2022
Editor: University of chemistry and technology, Prague

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

Autores: Norbert Krisztián Tóth
Publicado en: MSc thesis of energy engineering MSc student, 2023, Página(s) 1-83
Editor: 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

Autores: Daniela Marušáková
Publicado en: 2024
Editor: PhD thesis

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

Autores: Eva Bažantová
Publicado en: 2024
Editor: BSc thesis

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

Autores: Balázs Kiss
Publicado en: MSc thesis of energy engineering MSc student, 2024, Página(s) 1-68
Editor: 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

Autores: Candidate: Sara Kassem Tutors: Walter Ambrosini, Andrea Pucciarelli
Publicado en: 2024
Editor: Università di Pisa

Corrosion testing in supercritical water

Autores: Petr Čech
Publicado en: BSc degree thesis, 2022, Página(s) 31
Editor: University of chemistry and technology, Prague

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

Autores: Petr Čech
Publicado en: 2024
Editor: MSc thesis

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

Autores: Petr Čech
Publicado en: MSc degree thesis, 2024
Editor: University of chemistry and technology

Buscando datos de OpenAIRE...

Resultado final

Publicaciones

Compartir esta página Compartir esta página en las redes sociales

Descargar Descargar el contenido de la página