I agree that this site is using cookies. You can find further informations
here
.
X
Login
Merkliste (
0
)
Home
About us
Home About us
Our history
Profile
Press & public relations
Friends
The library in figures
Exhibitions
Projects
Training, internships, careers
Films
Services & Information
Home Services & Information
Lending and interlibrary loans
Returns and renewals
Training and library tours
My Account
Library cards
New to the library?
Download Information
Opening hours
Learning spaces
PC, WLAN, copy, scan and print
Catalogs and collections
Home Catalogs and Collections
Rare books and manuscripts
Digital collections
Subject Areas
Our sites
Home Our sites
Central Library
Law Library (Juridicum)
BB Business and Economics (BB11)
BB Physics and Electrical Engineering
TB Engineering and Social Sciences
TB Economics and Nautical Sciences
TB Music
TB Art & Design
TB Bremerhaven
Contact the library
Home Contact the library
Staff Directory
Open access & publishing
Home Open access & publishing
Reference management: Citavi & RefWorks
Publishing documents
Open Access in Bremen
zur Desktop-Version
Toggle navigation
Merkliste
1 Ergebnisse
1
Thermal hydraulic analysis in triangular sub-channel for 3M..:
, In:
International Conference on Green Energy, Computing and Intelligent Technology (GEn-CITy 2023)
,
Husna, A. U.
;
Rafi, M. M. H.
;
Tonny, I. J.
... - p. None , 2023
Link:
https://doi.org/10.1049/icp.2023.1777
RT T1
International Conference on Green Energy, Computing and Intelligent Technology (GEn-CITy 2023)
: T1
Thermal hydraulic analysis in triangular sub-channel for 3MW TRIGA mark II research reactor
UL https://suche.suub.uni-bremen.de/peid=ieee-10269207&Exemplar=1&LAN=DE A1 Husna, A. U. A1 Rafi, M. M. H. A1 Tonny, I. J. A1 Faisal, F. A1 Nishat, M. M. A1 Marshad, I. A1 Ahmed, F. A1 Mollah, A. S. YR 2023 K1 computational fluid dynamics K1 finite volume methods K1 fission reactor coolants K1 fission reactor cooling K1 fission reactor core control K1 fission reactor design K1 fission reactor fuel K1 fission reactor safety K1 fission research reactors K1 heat transfer K1 turbulence K1 viscosity K1 CFD problems K1 finite volume method K1 nuclear fuel centerline temperature K1 nuclear reactor core K1 sub-channel analysis K1 thermal hydraulic analysis K1 thermal-hydraulic parameters K1 triangular shape subchannel K1 triangular sub-channel K1 TRIGA fuel rods K1 Triga Mark II research reactor SP None LK http://dx.doi.org/https://doi.org/10.1049/icp.2023.1777 DO https://doi.org/10.1049/icp.2023.1777 SF ELIB - SuUB Bremen
Export
RefWorks (nur Desktop-Version!)
Flow
(Zuerst in
Flow
einloggen, dann importieren)