97/01957 Statistical analysis of the FT Calhoun reactor coolant pump system

• Publisher: Elsevier Science
• Year: 1997
• Weight: 186 KB
• Volume: 38
• Category: Article
• ISSN: 0140-6701
• DOI: 10.1016/s0140-6701(97)87890-3

✦ Synopsis

97101952 Neutronic model for modal multichannel analysis of out-of-phase instability in boiling water reactor cores Hashimoto. K. ct al. Anrt. Nncl. &erg??, 1997, 24, (2) 99-l I I. This paper presents a neutronic model for linear multichannel analysis of out-of-phase (regional) instability in a BWR core. In this model, the zeropower transfer function of a spatial-harmonic mode. the nodal component of the harmonic amplitude and the node-wise feedback coefficients for the mode appear. Applying the modal expansion technique to a transient flux. we can formulate the ahove transfer function, nodal component and feedhack coefficients. We derive a lumped neutronic model by the reduction of the present multichannel model. Consequently. the lumped feedback coefficients for the first harmonic mode and the nodal component of the harmonic amplitude can he explicitly expressed. 97101953 Operating and test experience with EBBII, the IFR prototype Sackett, J. I. /'rdgre,r.~ 111 Nnclear Energ', 1997, 31, (l/2), I I I-129.