Generation IV Heavy Liquid Metal (HLM) fast reactors have steam generators inside the reactor vessel. Therefore, the interaction between the secondary side coolant (water) and the HLM (e.g. steam generator tube rupture) has to be considered as challenging safety issue in the design and also in the preliminary safety analysis of these reactor types. In this framework, the separate effect facility LIFUS5/Mod2, installed at ENEA Research Center, has a new test section with a geometry representative of the SG tube bundle of ELSY design steam generator. Experiments were executed to study the interaction between LBE and water, with boundary and initial conditions relevant of the SGTR accident, the potential for tube-to-tube rupture propagation, as well as to demonstrate the reliability of computer codes in simulating the phenomena of interest. The paper presents LIFUS5/Mod2 facility and its capabilities, results from the tests' series B1 and preliminary post-test calculations by SIMMER-III code. The experiments provide pressure, temperature and strain trends versus time at a frequency up to 10 kHz, suitable for the analysis of interaction phenomena and the code validation. The experimental pressure trends highlights a remarkable damping of wave propagation generated because the presence of the tube bundle (that was not damaged). Codes are applied for supporting the experimental campaign, the design of experiments and for the experimental data analysis. RELAP5/MOD3.3 supported the analyses of the facility water injection line. The post-tests are mainly based on the comparisons of the experimental and calculated pressure trends. SIMMER-III provided an excellent simulation of the first pressure peak resulting from the rupture of the injector.
|Publication status||Published - 2015|
|Event||16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States|
Duration: 1 Jan 2015 → …
|Conference||16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015|
|Period||1/1/15 → …|
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
Del Nevo, A., Giannini, N., Pesetti, A., & Forgione, N. (2015). Experimental and numerical investigations of interaction between heavy liquid metal and water for supporting the safety of LFR GEN. IV reator design. Paper presented at 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, Chicago, United States.