A study of preferred BWR oscillation mode using the STAIF code
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:89263
The determination of the preferred oscillation mode is an important boiling water reactor (BWR) stability issue. A summary of a numerical study of this problem using the STAIF code is presented in this paper. STAIF is a computer code implementation of a BWR stability analysis model in the frequency domain. The main output of the code is decay ratio, which is defined as the asymptotic limit of the ratio of successive maxima of power (or flow rate) following an initial perturbation. Therefore, a decay ratio greater than unity represents a diverging oscillation or unstable mode. The code calculates the individual channel thermal-hydraulic decay ratio, the core decay ratio; and the regional decay ratio.
- OSTI ID:
- 89263
- Report Number(s):
- CONF-941102--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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