Zobrazeno 1 - 10
of 46
pro vyhledávání: '"Bao-Wen Yang"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 12, Pp 5106-5117 (2024)
Mixing Vane Grid (MVG) is considered as one of the most important components in the fuel assembly which not only plays the role of supporting the rod bundles but also improves the Critical Heat Flux (CHF) in the reactor core. Modeling and measuring t
Externí odkaz:
https://doaj.org/article/97b8bf25dffc4d16bf83bc76ae0d6f80
Publikováno v:
Energy Science & Engineering, Vol 11, Iss 3, Pp 1005-1024 (2023)
Abstract In turbulent mixed convection conditions, flow and heat transfer can deteriorate under specific conditions, thus affecting the performance of the safety of the system, which could imperil the safety of the nuclear reactor. In this paper, by
Externí odkaz:
https://doaj.org/article/d3f1e00dab244a8a9b6bb53140a67c34
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2775-2787 (2021)
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, which cannot effectively simulate the flow field of the reactor core or other structures. This is true even for the system codes containing three-dimens
Externí odkaz:
https://doaj.org/article/05c6057b5a74490aa5b256ff79a8fb16
Publikováno v:
Thermal Science. 2022, Vol. 26 Issue 5B, p4095-4105. 11p.
Investigation on heat transfer characteristics of Pb–Bi/S–CO2 PCHE with different channel structures
Publikováno v:
Progress in Nuclear Energy. 161:104721
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::018ac8c93bf18f2618f5645961636b48
https://doi.org/10.1016/j.pnucene.2023.104721
https://doi.org/10.1016/j.pnucene.2023.104721
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2775-2787 (2021)
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, which cannot effectively simulate the flow field of the reactor core or other structures. This is true even for the system codes containing three-dimens
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d3735fb4ddd37abd8c570ec9b1d293dc
http://www.sciencedirect.com/science/article/pii/S1738573321001698
http://www.sciencedirect.com/science/article/pii/S1738573321001698
Publikováno v:
Nuclear Technology. 206:1253-1295
Subchannel code analysis is one of the key thermal-hydraulic approaches for nuclear reactor design and safety analysis. At present, subchannel codes are employed to compute local thermal-hydraulic ...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e6b3c65e5a42c9366876b730f1bcaa44
https://doi.org/10.1080/00295450.2020.1792753
https://doi.org/10.1080/00295450.2020.1792753
Publikováno v:
Annals of Nuclear Energy. 181:109531
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::349edaf28c290d742b58a6854a4bedc6
https://doi.org/10.1016/j.anucene.2022.109531
https://doi.org/10.1016/j.anucene.2022.109531
Publikováno v:
Progress in Nuclear Energy. 154:104485
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4d1a2706f646cdcc7a3cc6e9cc31b39b
https://doi.org/10.1016/j.pnucene.2022.104485
https://doi.org/10.1016/j.pnucene.2022.104485
Autor:
Bao-Wen Yang, Sipeng Wang
Publikováno v:
Annals of Nuclear Energy. 131:185-195
The study of natural circulation is attracting more and more attention of researchers and engineers for the improvement of the system safety. A lot of natural circulation systems are applied to new generation reactors which make reactor systems safer
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a1b649936ec0465dba72dfa9bbea13c4
https://doi.org/10.1016/j.anucene.2019.03.044
https://doi.org/10.1016/j.anucene.2019.03.044