CFD Analysis of Core Bypass Flow and Crossflow in the Prismatic Very High Temperature Gas-cooled Nuclear Reactor /

Bibliographic Details

Main Author:	Wang, Huhu (Author)
Other Authors:	Hassan, Y. A. (Thesis advisor)
Format:	Thesis eBook
Language:	English
Published:	[College Station, Texas] : [Texas A & M University], [2013]
Subjects:	Major Nuclear Engineering. Crossflow Bypass flow Prismatic VHTR
Online Access:	Link to OAK Trust copy