TY - JOUR
T1 - Self-propagating high-temperature synthesis of simulated An 3+-contained radioactive graphite in N2 atmosphere
AU - Lu, Xirui
AU - Dong, Faqin
AU - Chen, Mengjun
AU - Su, Sijin
AU - Wang, Xiaoli
AU - Wu, Yanlin
N1 - Funding Information:
The authors would like to thank financial supports from the National natural Science Foundation of China (Contract No.: 21007052); Foundation of Laboratory of National Defense Key Discipline for Nuclear Waste and Environmental Safety, Southwest University of Science and Technology (Contract No.: 11zxnk09) Key Lab of Ministry of Education for Radiation Physics and Technology, Sichuan University(Contract No.: 2011-03); Foundation for Youth, Southwest University of Science and Technology.
PY - 2013
Y1 - 2013
N2 - The self-propagation synthesis (SHS) technology is characterized exclusively in multiple aspects, including: higher reaction rate, simplified procedure, shortened flow-process, facilitated process, lower energy consumption and remote control. In order to evaluate the performance of the self-propagating high-temperature synthesis (SHS) to treat An 3+-contained radioactive graphite in N2 atmosphere, in our study, with the exothermic reaction (3C + 4Al + 3TiO2 = 2Al 2O3 + 3TiC + Q), we used the following raw powdery materials including graphite (C), aluminum (Al), titanium dioxide (TiO 2) and neodymium oxide (Nd2O3, where Nd 3+ was used to simulate An3+). After a serial pretreatment including mixing, refinement and formation, a self-developed SHS reactive facility was used to prepare the simulated waste form for the An 3+-contained radioactive graphite. Then, X-ray diffractometer(XRD) and scanning electron microscope (SEM) were used to test and analyze the morphology, phase composition and solid solubility of the prepared waste forms. According to the results, the samples with the adding Nd2O 3 of 0∼16 wt% could maintain the self-sustainable reaction. And in the designed reaction, the Nd2O3 solid solubility was 1 wt%. The samples were mainly in pieces, with grain sized mainly in 5∼10μm. The samples without adding Nd2O3 content were composed of Al2O3, TiC, C, TiO2 and AlN. With adding Nd2O3 content of 1 wt%, the samples were composted of Al2O3, TiC, C, TiO2, AlN and NdAlO3. While in case of adding Nd2O3 content of over 1 wt%, the occurrence of the Nd2O3 phase was observed in the XRD patterns of the samples.
AB - The self-propagation synthesis (SHS) technology is characterized exclusively in multiple aspects, including: higher reaction rate, simplified procedure, shortened flow-process, facilitated process, lower energy consumption and remote control. In order to evaluate the performance of the self-propagating high-temperature synthesis (SHS) to treat An 3+-contained radioactive graphite in N2 atmosphere, in our study, with the exothermic reaction (3C + 4Al + 3TiO2 = 2Al 2O3 + 3TiC + Q), we used the following raw powdery materials including graphite (C), aluminum (Al), titanium dioxide (TiO 2) and neodymium oxide (Nd2O3, where Nd 3+ was used to simulate An3+). After a serial pretreatment including mixing, refinement and formation, a self-developed SHS reactive facility was used to prepare the simulated waste form for the An 3+-contained radioactive graphite. Then, X-ray diffractometer(XRD) and scanning electron microscope (SEM) were used to test and analyze the morphology, phase composition and solid solubility of the prepared waste forms. According to the results, the samples with the adding Nd2O 3 of 0∼16 wt% could maintain the self-sustainable reaction. And in the designed reaction, the Nd2O3 solid solubility was 1 wt%. The samples were mainly in pieces, with grain sized mainly in 5∼10μm. The samples without adding Nd2O3 content were composed of Al2O3, TiC, C, TiO2 and AlN. With adding Nd2O3 content of 1 wt%, the samples were composted of Al2O3, TiC, C, TiO2, AlN and NdAlO3. While in case of adding Nd2O3 content of over 1 wt%, the occurrence of the Nd2O3 phase was observed in the XRD patterns of the samples.
KW - Graphite
KW - Nuclear wastes
KW - Radioactivity
KW - SHS
UR - http://www.scopus.com/inward/record.url?scp=84898722503&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84898722503&partnerID=8YFLogxK
U2 - 10.1016/j.egypro.2013.07.224
DO - 10.1016/j.egypro.2013.07.224
M3 - Conference article
AN - SCOPUS:84898722503
VL - 39
SP - 365
EP - 374
JO - Energy Procedia
JF - Energy Procedia
SN - 1876-6102
T2 - 3rd International Conference on Asian Nuclear Prospects, ANUP 2012
Y2 - 16 October 2012 through 19 October 2012
ER -