GUO Lixiao¹，LIANG Dong¹，WANG Xiujuan²，DENG Shaogang¹，ZHOU Dawei²，ZHANG Yuhang¹，LIANG Yu¹

(1. China Institute for Radiation Protection, Taiyuan 030006, China;2. Huaneng Shandong Shidao Bay Nuclear Power Co. Ltd, Weihai 264300, China)

Abstract: In order to study the deposition behavior of graphite dust in high temperature gas cooled reactor (HTGR), a helium experimental loop was constructed and a steam generator head and a heat exchange unit simulator were designed. The deposition of graphite dust carried by helium gas in the steam generator of HTGR was studied. The deposition amount and distribution of graphite dust at the bottom of the steam generator and the heat exchange unit of the steam generator at different flow rates and temperatures were analyzed. The results show that there will be a large amount of graphite dust residue in the manhole of the steam generator, and the deposition at the lower part of the heat exchanger unit of steam generator is larger than that in the upper part. It is estimated that the saturated deposition in a single heat exchanger unit is about 222.6 g.

Keywords: high temperature gas cooled reactor; graphite dust; deposition experiment; steam generator

中图分类号：TL76

文献标志码：A

收稿日期： 2018-09-17，修回日期：2018-11-06，在线出版时间：2019-01-08 08:54。

基金项目：华能集团科技项目，编号：HNKJ-H18。

第一作者简介：郭丽潇(1988—)，男，助理研究员，研究方向为核设施退役与环境整治。E-mail：glxxy0303@163.com。

文章编号：1008-5548(2019)02-0047-07

DOI:10.13732/j.issn.1008-5548.2019.02.009