会议专题

EXPERIMENTAL FACILITIES FOR MATERIALS AND THERMODYNAMIC RESEARCH Technological Experimental Circuits

Many research activities are now realized and planned in Research Centre Rez and Nuclear Research Institute. The SuperCritical Water Loop (SCWL) newly installed in the Nuclear Research Institute Re? ((U)JV (R)e(z)) is an experimental facility for materials testing under radiation; active tests shall follow after successful out-of-pile operation and installation of the loop in the research reactor LVR-15 on site of the Institute. The main parameters are 25MPa pressure and 600℃ temperature in core. In the same time schedule a He-cooled loop was realized, with the goal of materials testing, including the effect of radiation, presence of impurities in He and high temperatures. The main parameters are 7MPa pressure and 900℃. Various primary He impurity levels shall be tested. Supported by the EU Structural funds, it is planned to build several technological experimental circuits. The Technological Experimental Circuits research program deals with several experimental facilities that are necessary for developing the following GIV Nuclear Reactor systems:-reactor cooled by supercritical water; a fuelled loop is planned for complex experiments aimed at confirming neutronic and thermohydraulic properties of such systems;-reactor cooled by high-temperature helium; the effort is to test the means for He purification, as well as heat exchanger and turbomachinery development;-fast reactor cooled by sodium combined with a secondary circuit cooled by supercritical carbon dioxide in the Brayton Cycle. Research related to CO2 conversion cycles constitutes a specific program supported by extensive previous experience, from which certain specific experimental results will be discussed.

Experimental research loop materials thermodynamic supercritical

P. Hájek R. V(s)olák M. Ru(z)icková

Research Centre Re(z) Ltd. 25068 Husinec-Re(z) 130, Czech Republic

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1774-1786

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)