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Wang X.-Q.,Chengdu University of Technology | Wang X.-Q.,Sichuan Environmental Protection Engineering Co. | Tuo X.-G.,Southwest University of Science and Technology | Zhou H.,China Institute of Atomic Energy | And 4 more authors.
He-Huaxue yu Fangshe Huaxue/Journal of Nuclear and Radiochemistry | Year: 2013

Glass vitrification technology will be used to treat high level liquid waste (HLLW) of Sichuan Environment and Protection Engineering Co. Ltd. (SEPEC). But this kind of HLLW contains high-sulfur and high-sodium, it slows down dynamitic process of the form of glass, restricts oxide loading of the waste glass, and causes yellow phase. That impair the quality of waste glass. Using simulants include many kinds of glass formulations are prepared accordingly to contents of HLLW, and researched and verificated. Decreasing the contents of Si and B in basic glass to raise contain Na2SO4 in waste glass; adding Sb2O5 and V2O5 content to increase oxygen ion in molten glass to increase its basicity. After compared the glass formulations and make improvements in laboratory, then the recommend formulation is given. Using this kind of glass formulation to do cold test on PVA facility to test the process properties and quality of waste glass, without accumulation of a separating yellow phase, the results meet the requests of its standards. Project of SEPEC (VPC) takes this kind of final glass formulation in its basic design documentation. Source


Wu L.,Southwest University of Science and Technology | Xu D.,Southwest University of Science and Technology | Li Y.-X.,Southwest University of Science and Technology | Teng Y.-C.,Southwest University of Science and Technology | Liu Z.-Q.,Sichuan Environmental Protection Engineering Co.
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2014

Nd-doped zirconolite-based glass-ceramics were prepared by melting-heat treatment technique. The effects of heat treatment processing on phase structure of the glass-ceramics were investigated. The leaching properties of the glass-ceramics were also evaluated by static leaching experiments (product consistency test, PCT). The results show that glass transformation temperature (Tg) and crystallization temperature of the glass-ceramics are about 580℃ and 740℃, respectively. CaTiO3 phase forms easily when the glass-ceramics were prepared by two-step method, i.e. the glass was prepared first, and then it was heat-treated at the crystallization temperatures. 2M-zirconolite phase can be obtained by one-step method, i.e. the heat-treatment immediately followed by the melting process. In addition, the zirconolite crystals exhibit a dendritic shape. The normalized mass loss of B and Na in the glass-ceramics remains almost unchanged (about 1 mg/m2) after 14 days, while the normalized mass loss of Nd reaches stable value (about 0.2 mg/m2) after 28 days. The normalized mass loss of B, Na, and Nd in the glass-ceramics is an order of magnitude lower than that of borosilicate glasses, respectively. ©, 2014, Yuanzineng Kexue Jishu/Atomic Energy Science and Technology. All right reserved. Source


Yang G.,Southwest University of Science and Technology | Tuo X.-G.,Southwest University of Science and Technology | Tuo X.-G.,Chengdu University of Technology | Cheng Z.,Sichuan Environmental Protection Engineering Co.
Hedianzixue Yu Tance Jishu/Nuclear Electronics and Detection Technology | Year: 2015

Tomographic Gamma Scanning is the main analytical method of nuclear waste in drum Non-Destructive-Assay. It can accurately measure the nuclides of the non-uniform nuclear waste with middle or high density in the drum. This paper reviews the research status of Tomographic Gamma Scanning of nuclear waste in drum at home and abroad, summaries the domestic researches at the existing basis and the progresses made, and gives a brief analysis of Tomographic Gamma Scanning's development trend. Research and development direction of Tomographic Gamma Scanning and the domestic problems faced by Tomographic Gamma Scanning of nuclear waste in drum are summarized, and solutions to these problems are briefly offered. ©, 2015, Atomic Energy Press. All right reserved. Source

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