Modifications Made to the MELCOR Code for Analyzing Lithium Fires in Fusion Reactors

Merrill, Brad Johnson

Idaho National Laboratory

关键词: Modifications;    Thermonuclear Reactors;    Recommendations;    Transport Fusion Reactor;    Transport Properties;   

DOI  :  10.2172/911471
RP-ID  :  INEEL/EXT-00-00489
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911471

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report documents initial modifications made to the MELCOR code that allows MELCOR to predict the consequences of lithium spill accidents for evolving fusion reactor designs. These modifications include thermodynamic and transport properties for lithium, and physical models for predicting the rate of reaction of and energy production from the lithium-air reaction. A benchmarking study was performed with this new MELCOR capability. Two lithium-air reaction tests conducted at the Hanford Engineering Development Laboratory (HEDL) were selected for this benchmark study. Excellent agreement was achieved between MELCOR predictions and measured data. Recommendations for modeling lithium fires with MELCOR and for future work in this area are included in this report.