Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
8068250 | Annals of Nuclear Energy | 2015 | 6 Pages |
Abstract
An optimized process for tritium-containing waste water collection of High-Temperature Gas-cooled Reactor (HTGR) was developed and experimentally verified using the 10Â MW High-Temperature Gas-cooled Reactor-test module (HTR-10). Compared with the previous process, an auxiliary molecular sieve bed was added in helium purification regeneration system and new operation process was proposed to collect tritium-containing waste water. In this paper, the optimized process and verification experiment were presented in detail. In commissioning experiment of the improved HTR-10, a large quantity of high-dose tritium-containing waste water was successfully collected in the water separator of helium purification regeneration system, with the specific activity being 6.1Â ÃÂ 109Â Bq/L. The verification experiment confirms that the optimized process is effective and reliable for the demonstration plant design of High Temperature Gas-cooled Reactor-Pebble bed module (HTR-PM) to avoid the large emission of detrimentally radioactive waste water to the environment.
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Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Hua Chang, Zong-Xin Wu, Shi-Yi Guo, Xing-Tuan Yang,