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Computational Validation of Experiments with Molten-Salt Thorium-Uranium Fuel Compositions in MBIR Test Loop
Atomic Energy ( IF 0.5 ) Pub Date : 2020-09-01 , DOI: 10.1007/s10512-020-00687-3
V. Yu. Blandinskii , D. S. Kuzenkova

The results of calculations of the equilibrium isotopic composition of molten-salt fuel in an experimental channel of the MBIR reactor are presented. Two organizational variants of the fuel cycle for a molten-salt test loop are examined: with extraction of protactinium and without extraction of heavy nuclei. The results show that the maximum thermal power of the test loop channel can reach 12 MW. Reprocessing of the fuel salt at the rate 27.1 kg/day is necessary to maintain the thermal power at the level 1 MW. A brief description is given of the procedure for obtaining an equilibrium isotopic composition in the ISTAR software system.

中文翻译:

MBIR 测试回路中熔盐钍铀燃料组合物实验的计算验证

介绍了 MBIR 反应堆实验通道中熔盐燃料平衡同位素组成的计算结果。检查熔盐测试回路燃料循环的两种组织变体:提取镥和不提取重核。结果表明,测试回路通道的最大热功率可以达到12 MW。需要以 27.1 公斤/天的速度对燃料盐进行后处理,以将火力维持在 1 兆瓦的水平。简要说明了在 ISTAR 软件系统中获得平衡同位素组成的程序。
更新日期:2020-09-01
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