正硅酸锂陶瓷小球离线释氚实验研究

核聚变与等离子体物理 ›› 2011, Vol. 31 ›› Issue (3): 224-227.

正硅酸锂陶瓷小球离线释氚实验研究

肖成建，陈晓军，康春梅，高小玲，刘浚，古梅，罗阳明，汪小琳

(中国工程物理研究院核物理与化学研究所，绵阳 621900)

收稿日期:2011-03-06 修回日期:2011-05-24 出版日期:2011-09-15 发布日期:2011-09-09
作者简介:肖成建(1979-)，男，重庆永川人，助理研究员，博士研究生，核燃料循环与材料专业，主要从事放射化学分析和能源材料研究。
基金资助:
国家磁约束核聚变能研究专项(2010GB112004)；中国工程物理研究院科学发展基金(2010B0301035)

Out-of-pile tritium release experiments of lithium orthosilicate pebbles

XIAO Cheng-jian, CHEN Xiao-jun, KANG Chun-mei, GAO Xiao-ling, LIU Jun, GU Mei, LUO Yang-ming, WANG Xiao-lin

(Institute of Nuclear Physics and Chemistry, CAEP, Mianyang 621900)

Received:2011-03-06 Revised:2011-05-24 Online:2011-09-15 Published:2011-09-09

摘要/Abstract

摘要：

中国氦冷球床包层(CH HCSB TBM)初步采用Li₄SiO₄陶瓷小球作为氚增殖材料，实验研究了Li₄SiO₄陶瓷小球的中子辐照产氚性能。将冷冻成型法制备的Li₄SiO₄ 陶瓷小球置于反应堆中辐照100min，然后在离线释氚实验平台上进行退火行为研究。实验结果表明，在用He +1% H₂为载气，流速为100mL•min^-1，升温速率为5K•min^-1的实验条件下，氚气(HT+T₂)是Li₄SiO₄陶瓷小球的主要释氚形态，占总氚的70%左右(不包括自由氚中的氚气)，在400℃~700℃范围内出现两次释氚峰；氚化水(HTO+T₂O)所占比例小于20%，主要在300℃~500℃的低温段进行释放；氚在800℃前基本释放完，小球退火后的残氚量小于1%。冷冻成型干燥法制备的Li₄SiO₄陶瓷小球在300℃~700℃范围内有较好的释氚性能，氚残留量低，在聚变堆固态氚增殖包层设计中具有一定应用价值。

关键词: 正硅酸锂, 释氚, 固态氚增殖剂, 国际热核聚变实验堆

Abstract:

Lithium orthosilicate (Li₄SiO₄) pebbles are considered as the candidate tritium breeders of Chinese helium cooled solid breeder test blanket module (CH HCSB TBM). The post-irradiation annealing experiments of lithium orthosilicate ceramic pebbles, made by freezen-sintering process, have been performed in CAEP. The samples were purged with 100mL/min mixed gas of He +1% H₂, heated at a constant rate of 5K•min^-1 in a reactor tube. The results showed that tritium was released mainly as tritium gas (HT+T₂), the proportion was about 70% except that in free tritium released out before annealing, and there were two tritium release peaks from 400℃~700℃. On the other hand, percentage of tritiated water (HTO+T₂O) was less than 20%, and released at lower temperature region of 300℃~500℃. Tritium remained in the pebbles was less than 1% after 800℃ in annealing experiments, so Li₄SiO₄ pebbles made by freezen-sintering process have favorable tritium release performance, and have potential application in fusion reactor solid blanket system.

Key words: Lithium orthosilicate, Tritium release, Solid tritium breeder, ITER

中图分类号:

肖成建，陈晓军，康春梅，高小玲，刘浚，古梅，罗阳明，汪小琳. 正硅酸锂陶瓷小球离线释氚实验研究[J]. 核聚变与等离子体物理, 2011, 31(3): 224-227.

XIAO Cheng-jian, CHEN Xiao-jun, KANG Chun-mei, GAO Xiao-ling, LIU Jun, GU Mei, LUO Yang-ming, WANG Xiao-lin. Out-of-pile tritium release experiments of lithium orthosilicate pebbles[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2011, 31(3): 224-227.

参考文献

[1] 陈晓军, 王和义, 罗阳明, 等. CH HCSB TBM 中固体氚陶瓷增殖剂微球研究进展 [J]. 核聚变与等离子体物理, 2006, 26(3): 210-216.

[2] 朱德琼, 陈晓军, 彭述明. 固体氚增殖剂的制备及性能综述 [J]. 材料导报, 2008, 22(9): 72-76.

[3] Roux N, Tanaka S, Johnson C, et al. Ceramic breeder material development [J]. Fusion Engineering and Design, 1998, 41: 31-38.

[4] Kleykamp H. Chemical interactions in the EXOTIC-7 experiment [J]. J. Nucl. Mater., 1999, 273: 171-176.

[5] Piazza G, Erbe A, Rolli R, et al. Post-irradiation examinations of Li₄SiO₄ pebbles irradiated in the EXOTIC-8 experiment [J]. J. Nucl. Mater., 2004, 329-333: 1260-1265.

[6] 冯开明. ITER实验包层计划综述 [J]. 核聚变与等离子体物理, 2006, 26(3): 161-169.

[7] Kinjyoa T, Nishikawaa M, Yamashitaa N, et al. Chemical form of released tritium from solid breeder materials under the various purge gas conditions [J]. Fusion Engineering and Design, 2007, 82: 2147-2151.

[8] 杨本福, 万竟平, 曹小华, 等. 锂陶瓷γ-LiAlO₂放氚行为研究 [J]. 原子能科学技术, 1999, 33(5): 441-445.

[9] Munakata K, Shinozaki T, Inoue K, et al. Tritium release from lithium silicate pebbles produced from lithium hydroxide [J]. Fusion Engineering and Design, 2008, 83: 1317-1320.

[10] Munakata K, Shinozaki T, Inoue K, et al. Tritium release from lithium orthosilicate pebbles deposited with palladium [J]. J. Nucl. Mater., 2009, 386-388: 1091 -1094.

[11] 毛世奇. 氚在Li₂SiO₃中释放行为研究 [J]. 原子能科学技术, 1997, 31(5): 468-471.

[12] Tanaka S, Terai T, Yamawaki M. Study on tritium release from solid breeding materials using the research reactor “YAYOI” [J]. Nucl. Energy, 1998, 32(1-2): 71-95.

[13] 郝嘉琨. 聚变堆材料 [M]. 北京: 化学工业出版社, 2006, 12: 134-135.