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Identification of two-phase flow patterns in a nuclear reactor by the high-frequency contribution fraction

Conference · · Transactions of the American Nuclear Society; (USA)
OSTI ID:6791828

Recently, King et al. and Wang et al. analyzed the fluctuating characteristics of differential pressure and void fraction by the optimum modeling method and by spectral analysis, respectively. These two investigations presented some new concepts and deterministic criteria, which are based on purely empirical formulas, to identify two-phase flow patterns. These deterministic criteria on two-phase flow patterns' identification seem to show reasonable performance. In King's and Wang's studies, there are at least three problems that need further investigations for the applications to the nuclear reactor engineering field. These three problems are the following: 1. Is the response to a certain two-phase flow pattern, i.e., the fluctuating characteristics, of neutrons the same as that of differential pressure or void fraction 2. Could those criteria developed from air/water flow be allowed to identify steam/water two-phase flow patterns 3. Could those criteria be applied to identify two-phase flow patterns in rod bundles In this paper, parts of the investigated results answer the first problem, and detailed comparisons with the previous work of the authors are given on a variety of items.

OSTI ID:
6791828
Report Number(s):
CONF-890604--
Journal Information:
Transactions of the American Nuclear Society; (USA), Journal Name: Transactions of the American Nuclear Society; (USA) Vol. 59; ISSN TANSA; ISSN 0003-018X
Country of Publication:
United States
Language:
English