Experimental Investigation of Subcooled Critical Flow Through Slits
Sandip Ghosh1, D. Mukhopadhyay2, Subha Mondal3 and S. K. Saha4
1Lecturer, Seacom Engineering College, Howrah 700 109, West Bengal, India.
pleasant_sandy@yahoo.co.in
2Scientific Officer, Reactor Safety Divison, Bhabha Atomic Research Centre, Mumbai, India.
dmukho@barc.gov.in
3Lecturer, Birbhum Institute of Engineering & Technology, Siuri, Birbhum, West Bengal, India.
subhamondal53@gmail.com
4Professor, Mechanical Engineering Department, Jadavpur University, Kolkata 700 032, India.
Sahasamir7@yahoo.com
ABSTRACT
The present work is an experimental investigation of the critical flashing flow of initially subcooled water through circumferential slits in pipes. The study provides first hand information about the prediction of leak flow rates in piping and pressure vessels retaining high temperature and pressure. The dedicated experimental facility loop simulates the thermal hydraulic condition of Pressurized Heavy Water Reactors (PHWR). The critical flow characteristics found for varying leakage cross sections at different stagnation pressure and different degree of sub-cooling has been demonstrated in this paper.
Full Text (PDF)
|
