C/C composites coated with SiC were introduced for the irradiation measurement at high temperature in Thorium Molten Salt Reactor-Solid Fuel (TMSR-SF) due to their excellent performance as an irradiation carrier of activation foil.
Purpose:
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This study aims at the effects of C/C composites to activation foils.
Methods:
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Based on the characteristics and service environment of C/C composites
component test and thermos analysis were carried out by element gravimetric density (GD) and calorimeter respectively to verify whether they would have influence on the irradiation results. Neutron irradiation experiment for activation foils with/withou
t C/C composites was performed in a horizontal radial hole of uranium zirconium hydride reactor. And the activation rates of mononuclear were calculated respectively.
Results:
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Experimental results show that SiC coating is essential for C/C composites to enhance oxidation resistance. The activation rate of mononuclear with C/C composites was reduced slightly. When the thickness of C/C was of mm-level
the decrement of activation rate for mononuclear was less than 10%.
Conclusion:
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C/C composites coated with SiC could be used as carrier materials for activation foils at high temperature when the carrier wall is thin. The results of irradiation could be corrected based on the measurement of C/C composites.
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references
周 雪梅 . 钍基熔盐堆中子能谱测量方法的研究 . 北京:中国科学院大学 , 2013 .
ZHOU Xuemei . Study of neutron energy spectrum for Thorium Molten Salt Reactor . Beijing:University of Chinese Academy of Sciences , 2013 .
SHI Yongqian . Experimental technology of neutronics in nuclear reactor . Beijing:Atomic Energy of China Publishing Press , 2011 . 343 - 345 .
Zhou X M , Liu G M , Li D , . Using activation method to measure neutron spectrum in an irradiation chamber of a research reactor . Nuclear Science and Techniques , 2014 . 25 ( 1 ): 010603 .