生产堆乏燃料后处理厂高放废液铸石固化工艺及配方的初步研究  

FEASIBILITY STUDY ON CASTING ROCK SOLIDIFICATION OF DEFENSE HIGH LEVEL WASTE

作　　者：程理[1] 杜大海[1] 龚立[1] 张英萍[1] 张吉富[1] 赵湘林 孙先荣[1] 

机构地区：[1]中国辐射防护研究院,北京核工程研究设计院

出　　处：《辐射防护》1994年第1期39-49,共11页Radiation Protection

摘　　要：通过对固化工艺的初步选择和配方的初步研究，在实验室中试制出生产堆乏燃料后处理厂产生的含高钠、高铝的高放模拟废液的铸石固化体。固化工艺路线为脱硝－煅烧－烧结，固化体容重为２．４８－２．６８ｇ／ｃｍ￣３，抗压强度为１３０－１８０ＭＰａ，固化体的抗浸出性能次于含Ｎａ＿２Ｏ１％－２％的ＳＹＮＲＯＣ－Ｃ，优于硼硅酸盐玻璃固化体。固化体的矿相有待于进一步的验证。The preliminary study on the formulation and technological process of castingrock solidification of defense HLW was carried out in lab.and the casting rock solidifiedproduct of defense HLW containing high contents of Na_2O and Al_2O_3 was prepared. The selected technological process was denitration-calcination-sintering. For the product with Na_2Oloading of 10%(wt),the bulk density was 2. 48-2. 68 g/cm￣3,the compression strength 130-180 MPa. Its leaching rate was slightly higher than that of SYNROC-C with Na_2O loadingof 1-2%(wt ) and lower than that of borosilicate glass waste form. The mineral phase ofthe product need to be identified further.

关 键 词：高放废液 固化 铸石 放射性废物 

分 类 号：TL941.11[核科学技术—辐射防护及环境保护]