Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Francesco Vitillo"'
Autor:
Khwansiri Ninpan, Shuzhang Huang, Francesco Vitillo, Mohamad Ali Assaad, Lies Benmiloud Bechet, Robert Plana
Publikováno v:
Algorithms, Vol 17, Iss 6, p 230 (2024)
This paper proposes a heuristic approach for managing complex construction projects. The tool incorporates Primavera P6 EPPM and Synchro 4D, enabling proactive clash detection and resolution of spatial conflicts during concurrent tasks. Additionally,
Externí odkaz:
https://doaj.org/article/3b543f651baa40a4848bc1423820e7f3
Publikováno v:
International Journal of Heat and Fluid Flow. 58:30-39
In the framework of CEA R&D program to develop an industrial prototype of sodium-cooled fast reactor named ASTRID, the present work aims to propose an innovative compact heat exchanger technology to provide solid technological basis for the utilizati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b6d6cc1f53d7998a4fd228102200a3e
https://doi.org/10.1016/j.ijheatfluidflow.2015.11.006
https://doi.org/10.1016/j.ijheatfluidflow.2015.11.006
Publikováno v:
Computers & Mathematics with Applications. 70:2238-2251
Computational fluid dynamics is nowadays a primary tool for a variety of engineering applications. Aeronautic, chemical, nuclear, marine engineering use available models to provide high technological products. Isotropic Reynolds-average Navier-Stokes
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6651b9d05be7a46bb5de518715cbc721
https://doi.org/10.1016/j.camwa.2015.08.023
https://doi.org/10.1016/j.camwa.2015.08.023
Publikováno v:
NURETH 16-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
NURETH 16-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2015, Chicago, United States
Scopus-Elsevier
NURETH 16-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2015, Chicago, United States
Scopus-Elsevier
International audience; In the framework of the development of the ASTRID Sodium-cooled Fast Reactor prototype, the CEA is studying the technical feasibility of adopting a Brayton power conversion cycle to eliminate the sodium-water interaction hazar
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::aaec8a59cc457c4b18d4553b6cbcc4ab
https://hal-cea.archives-ouvertes.fr/cea-02509256
https://hal-cea.archives-ouvertes.fr/cea-02509256
Publikováno v:
Scopus-Elsevier
In the framework of CEA R&D program to develop the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID), the present work aims to demonstrate the industrial interest of an innovative compact heat exchanger technology. In fact,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2e159748f19625c503ea6fd243ee375c
http://www.scopus.com/inward/record.url?eid=2-s2.0-84937413314&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-84937413314&partnerID=MN8TOARS
Publikováno v:
Scopus-Elsevier
International Congress on Advances in Nuclear Power Plants (ICAPP 2014)
International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Apr 2014, CHARLOTTE, United States
International Congress on Advances in Nuclear Power Plants (ICAPP 2014)
International Congress on Advances in Nuclear Power Plants (ICAPP 2014), Apr 2014, CHARLOTTE, United States
In the framework of the Gas-Power Conversion System for the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) project design, works done at CEA are focused on the design of the sodium-gas heat exchanger. Compact plate heat e
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::da8d36355b0e02443099955ba52efcad
http://www.scopus.com/inward/record.url?eid=2-s2.0-84907075473&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-84907075473&partnerID=MN8TOARS