Using the TRAC-BF1 time domain code for GE SBWR preliminary stability analysis

Journal Article · Sat Dec 31 00:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:75999

Lu, S; Baratta, A J; Robinson, G E; Mahaffy, J H

Reactor components of General Electric`s simplified boiling water reactor (SBWR) are described. The use of the TRAC-BF1 model to model vessel internal flow and fuel aassemblies is discussed. A possible unstable power oscillation of the SBWR was identified under reduced pressure and high operating power conditions. Further studies are need to explore the stability boundary of this reactor during startup. Multidimensional reactor kinetics models should be used to give more detailed reactor kinetics information.

• OSTI ID: 75999
• Report Number(s): CONF-940602-; ISSN 0003-018X; TRN: 95:003867-0176
• Journal Information: Transactions of the American Nuclear Society, Vol. 70; Conference: 35. annual meeting of the American Nuclear Society, New Orleans, LA (United States), 11-16 Jun 1994; Other Information: PBD: 1994
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
22 NUCLEAR REACTOR TECHNOLOGY
BWR TYPE REACTORS
REACTOR SAFETY
REACTOR COMPONENTS
T CODES
REACTOR STABILITY
REACTOR KINETICS