Advanced nuclear reactor safety analysis : the simulation of a small break loss of coolant accident in the simplified boiling water reactor using RELAP5/MOD3.1.1 /

(GE) in their Standard Safety Analysis Report (SAR) for the

Bibliographic Details

Main Author:	Faust, Christophor Randall, 1957-
Format:	Thesis eBook
Language:	English
Published:	[Place of publication not identified] : [publisher not identified] ; 1995.
Subjects:	Major nuclear engineering.
Online Access:	Link to OAKTrust copy