학술논문
Verification of IVA5 computer code for melt-water interaction analysis: Part 1
Document Type
Conference
Author
Source
Conference: 33rd National Heat Transfer Conference NHTC'99, Albuquerque, NM (US), 08/15/1999--08/17/1999; Other Information: PBD: 1999; Other Information: In: Proceedings of the 33rd national heat transfer conference NHTC'99, by Jensen, M.K.; Di Marzo, M. [eds.], [1150] pages.
Subject
Language
English
Abstract
In order to qualify IVA5 for applications in the field of the melt-water interactions in nuclear reactor safety, the author analyzed the achievable accuracy by predicting phenomena that are within this class. Comparison with a variety of experiments ranging from simple material relocation phenomena to highly violent explosions qualified IVA5 as a code representing the state-of-the-art in the field of the multiphase flows. The code is capable of predicting multiphase flow behavior in complicated geometries and industrial networks. The code is able to predict melt-water interaction in well quantified uncertainty region. Reducing the uncertainty band needs future sophistication in the directions specified in this work.