Development of the SPECTRA Code for Lead-Cooled Systems and Application to Operational Transients of the ELSY Reactor
An important feature of the Lead-cooled Fast Reactor is the enhanced safety that results from the choice of molten lead as a relatively inert coolant. Moreover, as with other fast systems, fuel sustainability is greatly enhanced by the conversion capabilities of the LFR fuel cycle. Following this option, the Specific Targeted Research ELSY Project (European Lead-cooled System) of the Euratom 6th Framework Programme aims to demonstrate that it is possible to design a competitive and safe fast critical reactor using simple engineered technical features. In the design procedure, thermal-hydraulic codes such as SPECTRA are applied to specific conditions to insure that reactor performance and safety are achieved. SPECTRA (Sophisticated Plant Evaluation Code for Thermal-hydraulic Response Assessment) is a computer program developed at NRG and designed for thermal-hydraulic analyses of nuclear or conventional power plants. As a consequence of using liquid lead as a coolant instead of water in both liquid and vapour phases, the SPECTRA code needed to be modified. The paper presents the main two modifications that were implemented in SPECTRA, namely, the thermo-physical properties of liquid lead and heat transfer correlations for different geometries and configurations. As an application, SPECTRA is used for the analysis of operational transients of the ELSY reactor in Beginning Of Cycle conditions. The SPECTRA results are shown to be in good agreement with the design values during shut-down and start-up operations
Liquid lead thermal-hydraulic code operational transients ELSY reactor.
J.R. Jonnet M.M. Stempniewicz P.H. Wakker
Nuclear Research and consultancy Group, Safety & Power PO Box 9034, 6800ES, Arnhem, The Netherlands
国际会议
上海
英文
450-461
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）