LWR core thermal-hydraulic analysis : assessment and comparison of the range of applicability of the codes COBRA IIIC/MIT and COBRA IV-I

Based on the M.S. thesis of the first author in the M.I.T. Dept. of Nuclear Engineering, 1978.

Bibliographic Details
Main Authors:	Kelly, J. E., Loomis, James N., Wolf, Lothar
Format:	Technical Report
Language:	en_US
Published:	MIT Energy Laboratory 2006
Subjects:	Nuclear fuel elements \|x Computer programs. Boiling water reactors.
Online Access:	http://hdl.handle.net/1721.1/31325

Internet

http://hdl.handle.net/1721.1/31325