会议专题

Employing of Best Estimate approach for testing of RBMK fuel rod model

Up to now the analyses of processes in RBMK fuel rods were prepared mainly by Russian specialists in Research and Development Institute of Power Energy (RDIPE-general designer of RBMK) and Kurchatov Institute using Russian in-house codes. This paper discuses the testing of RBMK-1500 reactor fuel rod model, developed in Lithuanian Energy Institute. For the modeling the FEMAXI-6 code, designed by Japanese scientists, was used. The materials of fuel and cladding and design of fuel assemblies in RBMK-type reactors are different comparing to vessel type light water reactors, for which the FEMAXI-6 code is developed. These differences in reactor materials and design were taken into account during the development of a model for analysis of processes in fuel rods and created model was tested. The testing (validation) of RBMK-1500 fuel rod model and adapted FEMAXI-6 code was performed comparing the FEMAXI-6 calculation results with the calculations performed by specialists from Kurchatov Institute (designers of RBMK). For benchmark the analysis of processes in fuel rods during normal plant operation was selected. The analysis was performed employing Best Estimate approach: the methodology developed in German company GRS and computer code of statistical methods SUSA were used. The results of sensitivity and uncertainty analysis shown, that thermal property of fuel rod has the most significant impact in the calculation results. This demonstrates, that for the more precision analysis of processes in RBMK-1500 fuel rod, it was necessary to adapt the FEMAXI-6 program code. Thus the usage of uncertainty and sensitivity analysis allowed to reduce the range of input parameters, which have the highest impact to calculation results.

RBMK-1500 fuel rod FEMAXI-6 uncertainty and sensitivity analysis

Eugenijus Uspuras Algirdas Kaliatka Tadas Kaliatka

Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute Breslaujos g. 3, LT-44403 Kaunas, Lithuania

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

2641-2656

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)