会议专题

Uncertainty and Sensitivity Analysis for the High Performance Light Water Reactor with TRACE and SUSA

The High Performance Light Water Reactor (HPLWR) is the European version of a Supercritical-Water-Cooled Reactor (SCWR). As one of the six Generation IV concepts, the HPLWR was under investigation regarding its technical and economical feasibility. Since the operational parameters of the HPLWR (coolant pressure 25 Mpa and outlet temperature around 800 K) are outside the usual range of current system tools like TRACE, RELAP5 or CATHARE, the codes need to be enhanced and validated. The main motivation of the present study is to evaluate the influence of input parameter changes (e.g., mass flow rate, power) on the calculated parameters (e.g., fuel centerline temperature, coolant heat up). The variability of the input or modelling parameters is due to two main reasons: on the one hand, certain quantities are affected by uncertainties in the modelling and in the selected correlations, on the other hand, operating parameters have not yet been fully optimized at the current design stage. Example of the first category includes the heat transfer coefficient (between the cladding and supercritical water) and the selected heat transfer correlation or the conductance of the helium gas gap (between the pellet and the clad internal surface), while example of the second one are the total moderator flow rate or the coolant inlet temperature. To consider these peculiarities in a consistent study, uncertainty and sensitivity methods need to be applied. These studies are important as they reveal that, for all combination of the input parameters within the selected range, the fuel and cladding temperature are below acceptable safety limits. During transients the situation might change. Uncertainty and sensitivity studies may help to identify the parameters with higher influence on the considered output parameter.

TRACE SUSA HPLWR Uncertainty Heat transfer

Wadim Jaeger Victor Hugo Sánchez Espinoza Lanfranco Monti Antonio Hurtado

Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology Hermann-von- Karlsruhe Institute of Technology, Institute of Nuclear and Energy Technologies Hermann-von-Helmholt Technical University of Dresden, Institute of Power Engineering 01062, Dresden, Germany

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

64-75

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)