SUBJECT:  
CFD simulation of turbulent flows inside a nuclear fuel subassembly

    
SUMMARY:

Complicated flow phenomena with energy exchanges in a nuclear fuel rod bundle are investigated numerically with the full use of computational fluid dynamics method based on either Direct Numerical Simulation (DNS) of turbulence, or Large Eddy Simulation (LES), or the Reynolds-Averaged Navier-Stokes equation approach. We look at a fuel pin subassembly of a sodium-cooled fast reactor in this study.

REQUIREMENTS:

Fundamental knowledge on nuclear engineering, thermal hydraulics, FORTRAN programming

PERIOD: Any time

RESPONSIBLE PERSON:
(address, phone, fax)
 
 
 
 
 

Prof. Hisashi Ninokata

Affiliation: Department of Nuclear Engineering, Tokyo Institute of Technology

Location: 2-12-1 O-Okayama, Meguro-Ku, Tokyo 152-8550 Japan

Email:hninokat@nr.titech.ac.jp

URL:http://www.nr.titech.ac.jp/NECourse