Assessment of the thermal-hydraulic technology of the transition phase of a core-disruptive accident in a LMFBR

Abstract

This report was prepared as an account of work sponsored by an agency of the United States uriocp /no oni A Government. Neither the United States Government nor any agency thereof, nor any of their NUntu/Un-dUI4 employees, makes any warranty, express or implied, or assumes any legal liability or responsi-BNL-NUREG-51621 bility for the accuracy, completeness, or usefulness of any information, apparatus, product, or AN, R-7 process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, . manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom-WUKuCj/CR 3014 mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the DE83 009098 United States Government or any agency thereof.

Advanced Reactor Safety Research Division. Quarterly progress report, April 1-June 30, 1980

“…A comparison of the void and pressure profile measurements taken without and with the flow obstructions will enable us to evaluate the influence of the disturbances on the two-phase flow field characteristics • The first series of measurements was presented in a previous Quarterly Report (Ginsberg, 1980). In that report, void data are presented for a single flow conditions.…”