[1]林鵬,陸杰,劉夏杰,等.核電廠典型中低放射性廢物等離子體熔融處理試驗研究[J].中國材料進展,2016,(07):006-10.[doi:10.7502/j.issn.1674-3962.2016.07.04]
LIN Peng,LU Jie,LIU Xia Jie,et al.Investigation of Thermal Plasma Melting of Typical Intermediate and Low Level Radioactive Wastes from Nuclear Power Plant[J].MATERIALS CHINA,2016,(07):006-10.[doi:10.7502/j.issn.1674-3962.2016.07.04]
點擊復(fù)制
核電廠典型中低放射性廢物等離子體熔融處理試驗研究(
)
中國材料進展[ISSN:1674-3962/CN:61-1473/TG]
- 卷:
-
- 期數(shù):
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2016年第07期
- 頁碼:
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006-10
- 欄目:
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特約研究論文
- 出版日期:
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2016-07-31
文章信息/Info
- Title:
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Investigation of Thermal Plasma Melting of Typical Intermediate and Low Level Radioactive Wastes from Nuclear Power Plant
- 作者:
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林鵬; 陸杰; 劉夏杰; 陳明周; 呂永紅
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中廣核研究院有限公司
- Author(s):
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LIN Peng; LU Jie; LIU Xia Jie; CHEN Ming Zhou; LV Yong Hong
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China Nuclear Power Technology Research Institute
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- 關(guān)鍵詞:
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中低放射性廢物; 熱等離子體; 玻璃固化體
- DOI:
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10.7502/j.issn.1674-3962.2016.07.04
- 文獻標(biāo)志碼:
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A
- 摘要:
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本文選取國內(nèi)壓水堆核電廠兩種典型的中低放射性廢物開展等離子體熔融中試試驗，在1250℃溫度條件下熔融100min，熔制成完全玻璃態(tài)的固化體，兩種玻璃固化體的XRD衍射譜均呈現(xiàn)為典型的非晶態(tài)譜；并選取了非放射性的Co2O3、SrCO3、CsCl作為放射性核素示蹤劑，模擬放射性核素137Cs、90Sr、58Co、60Co在核電站放射性廢物等離子熔融處理過程中的包容情況；經(jīng)檢測，玻璃固化體物理性能、抗浸出性能以及機械性能滿足高放玻璃固化體要求，且優(yōu)于水泥固化體標(biāo)準(zhǔn)；最后對后續(xù)試驗進行了展望，并提出了需要進一步解決的問題。
- Abstract:
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In this pilot scale testing research, two typical intermediate and low level radioactive wastes from the nuclear power plant were vitrified with thermal plasma. Both samples were melted at 1250℃ for 100min, and the XRD patterns of both samples presented as the typical amorphous state. Co2O3, SrCO3,CsCl were been added to the original wastes as the radionuclide tracer for simulating the containment effect of radionuclide in the process of vitrification. The performance of physical, leaching and mechanical of resultant glass waste-forms were tested showing the comparable requirement with the hign level radioactive waste glasses and the better one than cement waste-form. Finally, we discussed the prospect of the current work and proposed issues to be resolved.
更新日期/Last Update:
2016-06-29