
Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project
Author(s) -
Brian Williams,
Jim C. P. Liou,
Hiral J. Kadakia,
Bill Phoenix,
Richard R. Schultz
Publication year - 2007
Language(s) - English
Resource type - Reports
DOI - 10.2172/900897
Subject(s) - stratified flow , nuclear engineering , flow (mathematics) , nuclear reactor , key (lock) , nuclear reactor core , water cooling , light water reactor , core (optical fiber) , two phase flow , stratified flows , reactor design , process (computing) , system safety , engineering , systems engineering , computer science , environmental science , mechanical engineering , reliability engineering , meteorology , physics , mechanics , telecommunications , turbulence , operating system , computer security
This project characterizes typical two-phase stratified flow conditions in advanced water reactor horizontal pipe sections, following activation of passive cooling systems. It provides (1) a means to educate nuclear engineering students regarding the importance of two-phase stratified flow in passive cooling systems to the safety of advanced reactor systems and (2) describes the experimental apparatus and process to measure key parameters essential to consider when designing passive emergency core cooling flow paths that may encounter this flow regime. Based on data collected, the state of analysis capabilities can be determined regarding stratified flow in advanced reactor systems and the best paths forward can be identified to ensure that the nuclear industry can properly characterize two-phase stratified flow in passive emergency core cooling systems