Providing the Basis for Innovative Improvements in Advanced LWR Reactor Passive Safety Systems Design: An Educational R&D Project

Williams, Brian G. ; Liou, Jim C. P. ; Kadakia, Hiral ; Phoenix, Bill ; Schultz, Richard R.

Idaho State University, Pocatello, ID

关键词: Eccs;    Stratified Horizontal Flow, Condensation-Induced Water Hammer, Ap600;    Nuclear Engineering;    Water Lwr Passive Safety;    22 General Studies Of Nuclear Reactors;   

DOI  :  10.2172/900897
RP-ID  :  DOE/ID/14500
RP-ID  :  FG07-03ID14500
RP-ID  :  900897

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.