Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

Login

Technical Meeting on the Safety Approach for Liquid Metal Cooled Fast Reactors and the Analysis and Modelling of Severe Accidents

13–17 Mar 2023
IAEA
Europe/Vienna timezone

Contact

Development of drift-flux correlations for vertical forward bubble column-type gas-liquid lead-bismuth two-phase flow

15 Mar 2023, 14:45
30m
CR4 (IAEA)

CR4

IAEA

IAEA Headquarters, Vienna, Austria

Speaker

Mr Di Wang (China Nuclear Power Technology Research Institute Co., Ltd.)
Country of origin China
Organization China Nuclear Power Technology Research Institute Co., Ltd.
Topic of the Abstract Subtrack 2 Analysis and Modelling of Severe Accidents for LMFR

Co-authors

Mr Yonggang Shen (China Nuclear Power Technology Research Institute Co., Ltd.) Dr Chengjie Duan (China Nuclear Power Technology Research Institute Co., Ltd.)

Presentation materials

【EVT2204904-WANG DI】 Development of drift-flux correlations for vertical forward bubble column-type gas-liquid lead-bismuth two-phase flow.pdf
【EVT2204904-WANG DI】 Development of drift-flux correlations for vertical forward bubble column-type gas-liquid lead-bismuth two-phase flow.pptx
Powered by Indico v3.2.9