Zobrazeno 1 - 10
of 42
pro vyhledávání: '"Dmitry Grishchenko"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 1052-1065 (2024)
Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure. Steam can be discharged into the pool through multi-hole spargers or blowdown pipes in both no
Externí odkaz:
https://doaj.org/article/04c92d28f20448cebcad8e76d99fcc2d
Autor:
Victor Hugo Sanchez-Espinoza, Stephan Gabriel, Heikki Suikkanen, Joonas Telkkä, Ville Valtavirta, Marek Bencik, Sören Kliem, Cesar Queral, Anthime Farda, Florian Abéguilé, Paul Smith, Paul Van Uffelen, Luca Ammirabile, Marcus Seidl, Christophe Schneidesch, Dmitry Grishchenko, Hector Lestani
Publikováno v:
Energies, Vol 14, Iss 19, p 6348 (2021)
This paper describes the main objectives, technical content, and status of the H2020 project entitled “High-performance advanced methods and experimental investigations for the safety evaluation of generic Small Modular Reactors (McSAFER)”. The m
Externí odkaz:
https://doaj.org/article/d995b2118c41404e84edd83e3c2ca090
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2015 (2015)
RELAP5 is a system thermal-hydraulic code that is used to perform safety analysis on nuclear reactors. Since the code is based on steady state, two-phase flow regime maps, there is a concern that RELAP5 may provide significant errors for rapid transi
Externí odkaz:
https://doaj.org/article/4d388888fd7b4860bec3520b85aad4c7
Publikováno v:
Annals of Operations Research
Annals of Operations Research, Springer Verlag, In press, 295, pp.535-560. ⟨10.1007/s10479-020-03811-5⟩
Annals of Operations Research, 2020, 295, pp.535-560. ⟨10.1007/s10479-020-03811-5⟩
Annals of Operations Research, Springer Verlag, In press, 295, pp.535-560. ⟨10.1007/s10479-020-03811-5⟩
Annals of Operations Research, 2020, 295, pp.535-560. ⟨10.1007/s10479-020-03811-5⟩
International audience; Progressive Hedging is a popular decomposition algorithm for solving multi-stage stochastic optimization problems. A computational bottleneck of this algorithm is that all scenario subproblems have to be solved at each iterati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::abf617bce86657dcd7e94ddae1ac81dc
https://doi.org/10.1007/s10479-020-03811-5
https://doi.org/10.1007/s10479-020-03811-5
Publikováno v:
Volume 4: Student Paper Competition.
The Steam injection through multi-hole spargers into the pressure suppression pool (PSP) is used in light water reactors to prevent containment over-pressure. The development of thermal stratification in the PSP can reduce its cooling capacity and re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6d807d3b2517a8a7b1a224dbea83eaf
https://doi.org/10.1115/icone28-65751
https://doi.org/10.1115/icone28-65751
The Pressure Suppression Pool (PSP) in a Boiling Water Reactor (BWR) is served as a heat sink to prevent containment over-pressure. The steam can be injected through the multi-hole spargers. The development of thermal stratification where a thermocli
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::87e0644fc5158a583f8994bbc8ef6b9d
https://doi.org/10.1115/1.0000590v
https://doi.org/10.1115/1.0000590v
Publikováno v:
Annals of Nuclear Energy. 132:442-450
The pressure suppression pool of a Nordic Boiling Water Reactor (BWR) serves as a heat sink to condense steam from the primary coolant system in normal operation and accident conditions. Thermal st ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d4f7d6470304063a3fb54d70253c4b2f
https://doi.org/10.1016/j.anucene.2019.04.054
https://doi.org/10.1016/j.anucene.2019.04.054
Publikováno v:
Nuclear Engineering and Design. 343:63-75
Sever accident mitigation strategy adopted in Nordic Boiling Water Reactors (BWRs) employs a deep water pool below the reactor vessel to fragment and quench core melt and provide long term cooling of the debris. One of the risks associated with this
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f55deda8bd37f8a43e09d5e705bd6f7d
https://doi.org/10.1016/j.nucengdes.2018.12.013
https://doi.org/10.1016/j.nucengdes.2018.12.013
Publikováno v:
Nuclear Engineering and Design. 341:306-325
Computational Fluid Dynamics (CFD) provides means for high-fidelity 3D thermal-hydraulics analysis of Generation IV pool-type nuclear reactors. However, to be used in the decision making process a proof of code adequacy for intended application is re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f5de11936a1bbed1883b0115b5a760e0
https://doi.org/10.1016/j.nucengdes.2018.11.015
https://doi.org/10.1016/j.nucengdes.2018.11.015
Publikováno v:
Nuclear Engineering and Design. 392:111773
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f7ac94b596f8a11f749366ad2d529b8e
https://doi.org/10.1016/j.nucengdes.2022.111773
https://doi.org/10.1016/j.nucengdes.2022.111773