Summary from “Aix-en-Provence 1992” and “Annapolis 1996” OECD/NEA/CSNI Specialists Meetings in Nuclear Thermal Hydraulics (English)
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In:
Nuclear Engineering and Design
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416
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2023
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Summary from “Aix-en-Provence 1992” and “Annapolis 1996” OECD/NEA/CSNI Specialists Meetings in Nuclear Thermal Hydraulics
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Contributors:Aksan, Nusret ( author ) / D'Auria, Francesco ( author )
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Published in:
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Publisher:
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Publication date:2023-09-26
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:Nuclear thermal hydraulics , Two-phase and multi-field flow modelling , Data analysis of experiments , Computer code validation matrices , Verification and validation of computer code models , International standard problem activities , Scaling and uncertainty analysis , Physical modelling improvements , Multi-physics activities , Multi-dimensional modelling , Computational fluid dynamics , Containment modelling and coupling with system computer codes
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Source:
Table of contents – Volume 416
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
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Performance analysis of irradiated thermo-mechanical coupled petal-shaped fuel rod under different power and heat transfer conditionsHe, Binxian / Zhang, Wenchao / Meng, Xiangfei / Sun, Jianchuang / Du, Lipeng / Cai, Weihua et al. | 2023
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Modeling single-phase transverse flows in a PWR rod bundle at low Reynolds numberFu, Qinjun / Bergeron, André / Fillion, Philippe / Davit, Yohan / Quintard, Michel et al. | 2023
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Investigation of reactivity control strategies for a micro-transportable gas-cooled thermal reactorChai, Xiang / Liu, Xinyue / Guan, Chaoran / Zhang, Tengfei / Liu, Xiaojing et al. | 2023
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Study of the impact of hydrides on the fracture toughness of Zr-2.5Nb alloyJanulionis, Remigijus / Dundulis, Gintautas et al. | 2023
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Influence of rebar couplers on the cracking behavior of reinforced concrete beamsBen-dahou, Amine / Ferrier, Emmanuel / Gabor, Aron / Michel, Laurent / Gardes, Rémi / Boisson, Richard / Poissonnet, Clément / Dolo, Jean-Marie et al. | 2023
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Irregular pentagon loop for nuclear reactor natural circulation system test apparatusHariyanto, Duwi / Permana, Sidik / Waris, Abdul / Mustari, Asril Pramutadi Andi / Kinoshita, Motoyasu / Aji, Indarta Kuncoro / Maulana, Alan / Setiadipura, Topan et al. | 2023
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FE modeling of the reconstructed Bituminated radioactive waste storage of Ignalina NPPEidukynas, V. / Dundulis, G. / Eidukynas, D. et al. | 2023
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Designing a system of boron concentration measurement in solution samples by the PGNAA facility of the Isfahan MNSR reactorJafari, M. / Jafari, H. / Choopan Dastjerdi, M.H. / Mokhtari, J. et al. | 2023
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Hydrogen distribution in a BWŔs RPV and Mark II drywell during the progression of a severe accident with and without emergency coolant injectionOrtiz-Villafuerte, Javier / Sáinz-Mejía, Eduardo / Xolocostli-Munguía, J. Vicente / Gómez-Torres, Armando M. / Sánchez-Mora, Heriberto et al. | 2023
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Optimization of preparation process and study on the properties and microstructures of nuclear natural graphite powder for HTR pebble fuel elementsTong, Xi / Gao, Huixun / Zhang, Shouchi / Zhou, Xiangwen / Liu, Bing et al. | 2023
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Mechanism and risk assessment of baffle-jetting-induced vibrations in fuel rodsGad-el-Hak, Ibrahim / Mureithi, Njuki / Karazis, Kostas / Painter, Brian et al. | 2023
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Analysis of main steam line break accident on a BWR test facility using TRACEYang, Ye / Hu, Mengyan / Zhang, Xueyan / Yang, Jun et al. | 2023
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Risk-informed design of advanced nuclear reactor: A target unavailability approachCastillo-Hernández, Orestes / Perdomo-Ojeda, Manuel / Grantom P.E., C.R. / Nelson, Pamela F. et al. | 2023
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Summary from “Aix-en-Provence 1992” and “Annapolis 1996” OECD/NEA/CSNI Specialists Meetings in Nuclear Thermal HydraulicsAksan, Nusret / D'Auria, Francesco et al. | 2023
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Two-phase CFD simulations of COSI tests and evaluation of condensation distributionRaverdy, Bruno et al. | 2023
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Irradiation performance of a U-7Mo in Al-Si matrix dispersion full-size fuel plate assemblyWoolstenhulme, N.E. / Robinson, A.B. / Nielsen, J.W. / Choi, Y.J. / Johnson, T.A. / Yim, J.S. / Tahk, Y.W. / Park, J.M. et al. | 2023
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Spanish R&D in dry storage of spent fuel: Outcomes and outlookFeria, F. / Aguado, C. / Benavides, J. / Canencia-Hernanz, R. / Cristobal-Beneyto, M. / Fernández García, J. / Galán, H. / González, C. / Hernandez-Avellaneda, A. / Herranz, L.E. et al. | 2023
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Decommissioning fund evaluation considering a multiple reactor siteMonteiro, Deiglys Borges / Moreira, João M.L. / Kobaiashi, Guiou et al. | 2023
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Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (T-H) characteristics of the MNSR research reactor fuel assemblyAl-Zain, Jamal / El Hajjaji, O. / El Bardouni, T. / Basfar, Ahmed A. / Alnaser, Ibrahim A. / Lahdour, M. / Galahom, A. Abdelghafar / Boulaich, Y. / Ahmed, Abdulaziz / Mira, Mohamed et al. | 2023
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Thermal-Hydraulic comparative analysis of G-III + BWR and PWR passive safety features under Loss of coolant accidentZhang, Xueyan / Hu, Mengyan / Peng, Cuiting / Zhang, Yixuan / Yang, Ye / Deng, Chengcheng / Yang, Jun et al. | 2023
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Anomaly detection in BWR fuel cell using neutron noise analysis techniques. Slow control rod detectionTorres, L.A. / Montalvo, C. / Gavilán, C.J. / García-Berrocal, A. et al. | 2023
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Validation of Pronghorn’s subchannel code using EBR-II shutdown heat removal tests: SHRT-17 and SHRT-45RTano, Mauricio / Kyriakopoulos, Vasileios / McCay, James / Arment, Tyrell et al. | 2023
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The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditionsAl-Yahia, Omar S. / Bernard, Matthew / Clifford, Ivor / Perret, Gregory / Bajorek, Stephen / Ferroukhi, Hakim et al. | 2023
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Extension of GeN-Foam to departure from nucleate boiling prediction and validation against the OECD/NRC PSBT benchmarkNiu, Yuhang / Alessandro, Scolaro / Fiorina, Carlo / Qin, Hao / Lazare, Gauthier / Wu, Yingwei / Tian, Wenxi / Su, G.H. et al. | 2023
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Development and validation of Loss of Coolant Accident (LOCA) simulation capability in the ENIGMA fuel performance code for zirconium-based cladding materialsRossiter, Glyn / Peakman, Aiden et al. | 2023
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Application of Modelica/TRANSFORM to system modeling of the molten salt reactor experimentFischer, Lorenz / Bureš, Lubomír et al. | 2023
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A machine learning diagnosis of the severe accident progressionSong, JinHo / Kim, SungJoong et al. | 2023
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Numerical simulation of transient boiling and void cross flow in non-uniformly heated 5 × 5 rod bundleOkawa, Riichiro / Furuya, Masahiro / Arai, Takahiro / Iiyama, Tsugumasa / Shirakawa, Kenetsu et al. | 2023
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Experimental and numerical investigation on dynamic characteristic of nozzle check valve and fluid-valve transient interactionZhao, Liang / Chang, Zhengbai / Mai, Chulin / Ran, Hong / Jiang, Jin et al. | 2023
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Challenges in high-fidelity thermal–hydraulic simulation of SFR cores: Insights and PACA-S4FR solutionsDong, Lingyu / Miao, Xue / Meng, Xiangling / Li, Yang / Dai, Chaohu / Sha, Jian / Ge, Nannan et al. | 2023
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Three-dimensional phase-field simulation of intergranular bubble evolution in UO2 during irradiationLan, Xun / Jiang, Yanbo / Sun, Dan / Liu, Wenbo / Li, Wenjie et al. | 2023
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Integral simulation of the first 3 weeks of severe accident at Fukushima Daiichi Unit 1 with SOCRAT code. Part I – Qualification of model and simulation of the initial phaseDolganov, Kirill S. et al. | 2023
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Modeling of quenching temperature with the effects of axial conduction resulting from quench front propagationHurley, Paul / Kim, Kyung Mo / Duarte, Juliana P. et al. | 2023
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Simulation of SN transport equation for hexagonal-z reactor using the COMSOL Multiphysics softwareWang, Yahui / Chen, Jiancheng / Li, Da / Shi, Leitai / Chi, Honghang / Ma, Yu et al. | 2023
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An algorithm for solving the equations of the Nodal Expansion Method in parallel using GPUMendes, J.M.S. / Heimlich, A. / De Lima, A.M.M. / Silva, F.C. et al. | 2023
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OECD/NEA/CSNI state-of-the-art report on scaling in system thermal-hydraulics applications to nuclear reactor safety and design (The S-SOAR)Mascari, F. / D'Auria, F. / Bestion, D. / Lien, P. / Nakamura, H. / Austregesilo, H. / Moon, S.K. / Reventos, F. / Umminger, K. / Reyes, J.N. et al. | 2023
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Autonomous search investigation for radioactive leaked source based on an updated infotaxis method during nuclear emergency rescueChen, Liwei / Zhou, Cong / Wang, Yu / Zong, Yiran / Lu, Tingting / Chen, Chunhua et al. | 2023
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Editorial Board| 2024
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Application of analytical wall functions to CFD analysis of condensation flowSoma, Shu / Ishigaki, Masahiro / Abe, Satoshi / Sibamoto, Yasuteru et al. | 2023
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Modified correlations for the Nusselt numbers at the boundaries of a bottom-heated molten metal layer in a stratified corium melt pool and an assessment of heat transfer conditions during a severe accidentLoktionov, Vladimir et al. | 2023
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Research on optimization scheme for boiling heat transfer models of mini-channels casing-pipes once-through steam generatorLi, Ang / Chen, Yuqing / Rao, Yuxian / Cai, Qi / Wang, Cong et al. | 2023
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Evaluation of the spatial self-shielding impact for TRISO-based nuclear fuel depletionMartin, Nicolas / Youinou, Gilles et al. | 2023
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Analytical model development for investigation on hydrogen management studies in the containment of a nuclear reactorKumar Sharma, Sanjeev / Kansal, Manoj / Chandraker, D.K. / Maheshwari, N.K. / Hajela, Sameer et al. | 2023
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Interplay of human factors and safety culture in nuclear safety for enhanced organisational and individual Performance: A comprehensive reviewFelix Orikpete, Ochuko / Raphael Ejike Ewim, Daniel et al. | 2023
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Study on bubble dynamics in sodium using three-dimensional MPS methodLiu, Xiaoxing / Xu, Yihua / Wang, Kai / Cheng, Songbai / Tong, Lili et al. | 2023
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Scope of conceptual development of Resilient supercritical Light water-cooled reactor (SCWR-R)Yamaji, Akifumi / Matsuoka, Koki / Sumida, Kota / Funatsu, Kohki et al. | 2023
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Research and analysis of the thermal and control characteristics of the plate-type fuel assembly for the supercritical CO2 reactorZhao, Fulong / Guo, Jia / Xie, Lin / Tian, Ruifeng / Tan, Sichao et al. | 2023