Uncertainty analysis of minimum vessel liquid inventory during a small-break LOCA in a B&W plant  an application of the CSAU methodology using the RELAP5 MOD3 computer code 
prepared by M.G. Ortiz, L.S. Ghan. 
 - Washington DC  Division of Systems Research  Office of Nuclear Regulatory Research  U.S. Nuclear Regulatory Commission :  1992 
 - 1 v. (various pagings),  ill.  28 cm. 
<br/><br/> "Date published: December 1992."  "EG & G Idaho, Inc."  "EGG-2665."  "Idaho National Engineering Laboratory."  "NUREG/CR-5818."  Distributed to depository libraries in microfiche.  Shipping list no.: 93-0363-M. 
<br/><br/>Includes bibliographical references. 
<br/><br/>Technical. 
<br/><br/><label>Subjects--Topical Terms: </label><br/>Nuclear reactors--Computer simulation.<br/>Pressurized water reactors--Loss of coolant
<br/><br/><label>Dewey Class. No.: </label>621.4834 UNC 1992 
<br/><br/><label>GPO Item No.: </label>1051-H-11 (MF) 
<br/><br/><label>Gov. Doc. Class. No.: </label>Y 3.N 88:25/5818