Plate fuel assemblies will be widely applied in the future because of their simple and compact structure and excellent heat exchange capability. When the plate fuel assemblies are used in a ship reactor, the effect of the ship motion on the reactor core thermal hydrodynamic must be investigated. In this paper, aiming at the rectangular shape of coolant channels in the assemblies, the numerical simulation of the flow and heat exchange in a rectangular channel in horizontal translation is carried out. Using the CFD Software and UDF code, the simulation model of the channel in horizontal translation with and without acceleration along its width direction is built up, and the related characteristics is analyzed and discussed. The results and conclusions are applicable and useful for the new type ship PWR design.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Analysis of Single Phase Flow and Temperature Fields in Rectangular Channel With Translation in Width
Lei Luo,
Lei Luo
Naval University of Engineering, Wuhan, Hubei, China
Search for other works by this author on:
Wenzhen Chen,
Wenzhen Chen
Naval University of Engineering, Wuhan, Hubei, China
Search for other works by this author on:
Zhiyun Chen,
Zhiyun Chen
Naval University of Engineering, Wuhan, Hubei, China
Search for other works by this author on:
Jianli Hao
Jianli Hao
Naval University of Engineering, Wuhan, Hubei, China
Search for other works by this author on:
Lei Luo
Naval University of Engineering, Wuhan, Hubei, China
Wenzhen Chen
Naval University of Engineering, Wuhan, Hubei, China
Zhiyun Chen
Naval University of Engineering, Wuhan, Hubei, China
Jianli Hao
Naval University of Engineering, Wuhan, Hubei, China
Paper No:
ICONE18-29280, pp. 269-273; 5 pages
Published Online:
April 8, 2011
Citation
Luo, L, Chen, W, Chen, Z, & Hao, J. "Analysis of Single Phase Flow and Temperature Fields in Rectangular Channel With Translation in Width." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 269-273. ASME. https://doi.org/10.1115/ICONE18-29280
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
ASME J of Nuclear Rad Sci (October,2023)
Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
ASME J of Nuclear Rad Sci (April,2017)
Analysis of Liquid-Cooled Heat Sink Used for Power Electronics Cooling
J. Thermal Sci. Eng. Appl (June,2011)
Related Chapters
Numerical Simulation Research on a Fixed Bed Gasifier
International Conference on Information Technology and Management Engineering (ITME 2011)
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
List of Commercial Codes
Introduction to Finite Element, Boundary Element, and Meshless Methods: With Applications to Heat Transfer and Fluid Flow