Convegni ATI - Accesso riservato soci CTI

Autore: V. Faluomi, F. D'Auria, S.N. Aksan

Collana: CA - 49 - Perugia 1994

Note:
In the framework of nuclear plant design and safety, one of the most important parameters to take into account for establishing the highest power available from a Nuclear Power Plant is the value of Critical Heat Flux (CHF) [1]. Large research efforts were made to develop empirical, semiempirical and theoretical methods to represent this phenomenon and to provide best estimate values (based on phenomenological methods) of CHF under different conditions, especially near the operational conditions of PWRs and BWRs. There are presently more than 300 different correlations in the literature that cover wide spectrum of occurrence of CHF, but still lacks an analytical theory for grouping the experimental data [2]. In this paper, some of the most used correlations in the thermal hydraulic system behaviour codes are analysed and compared to each other to show the differences in the modelling of the phenomenon considered, and the results are discussed considering the influence of the differences in relation to the thermalhydraulic safety of the Nuclear Power Plants.