LOCA and RIA simulating tests in Triga MT reactor of INR Pitesti

Abstract only, full text of publication follows: One of the main objectives of INR Pitesti Fuel Testing Program is to provide high quality experimental data for development and validation of computer codes and for improvement of the physical models used in these computer codes, thanks to the understanding and quantifying of the basic physical mechanisms. A large number of global and instrumented tests have been performed in TRIGA SS Reactor and TRIGA Pulse Reactor of INR Pitesti for detailed investigation of various aspects related to the thermal behaviour, fission product release and mechanical response of PHWR fuel elements under a variety of normal and accidental conditions. LOCA simulating tests with fresh and pre-irradiated fuel elements are planned to be performed in C2 tests capsule and in Loop A of TRIGA SS Reactor and new rapid overpower transient tests on fuel elements with pre-hydrided claddings are planned to be performed in C6 capsule of TRIGA Pulse Reactor in order to study behaviours of fuel elements during off-normal and postulated accident conditions such as loss-of coolant accident (LOCA) and reactivity-initiated accident (RIA). This paper reviews in-pile experiments performed and planed in TRIGA SS reactor and TRIGA Pulse reactor of INR Pitesti and presents some of the recent results obtained from these tests. (author)