Advances of computational fluid dynamics in nuclear reactor design and safety assessment / edited by Jyeshtharaj B. Joshi, Arun K. Nayak.
Series: Woodhead Publishing in energyPublisher: Description: xiii, 869 pages : illustrations (chiefly color) ; 23 cmContent type:- text
- unmediated
- volume
- 9780081023372
- 0081023375
- 621.48/3 23 A244
- TK9202 .A283 2019

Item type | Current library | Call number | Status | Notes | Date due | Barcode | |
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Central Library المكتبة المركزية | 621.483 A244 (Browse shelf(Opens below)) | Available | قاعة الكتب |
Includes bibliographical references and index.
Introduction -- Computational fluid dynamics -- CFD model development for two-phase flows -- Evaluation of safety of light-water-cooled reactors using CFD -- Design of passive safety systems for advanced reactors using CFD -- Modelling of core melt scenarios in nuclear reactors -- Application of CFD for assessment of containment safety -- Modeling of fire with CFD for nuclear power plants (NPPs) -- Applications of computational fluid dynamics in design of sodium-cooled fast reactors -- CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors -- Heat transfer and computational fluid dynamics for molten salt reactor technologies -- Conclusions and future recommendations.
Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants.-- Source other than the Library of Congress.