Abstract
Paper presents simulation of the upgraded ICE facility test P1 performed using COCOSYS and ASTEC lumped parameter codes. The experimental ICE facility was constructed at the Japan Atomic Energy Research Institute (JAERI) to obtain experimental data on the ingress-of-coolant event which could occur in the ITER. COCOSYS and ASTEC are computer codes used to simulate accident scenarios in the light water reactors. However, they’ve been also used for fusion safety applications and ASTEC is being extended to better address main accident sequences of fusion installations. It is shown in the paper that pressure and temperature evolutions of the main volumes were predicted with reasonable accuracy, however discrepancies in the suppression and drain volumes suggest underestimated vaporization rate.
Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
