The design and thermohydraulics study of the HTR-10 High Temperature Helium Experimental Loop

被引：10

作者：

Yang, Chen ^{[1
,2
]}

Fang, Chao ^{[1
,2
]}

Cao, Jianzhu ^{[1
,2
]}

机构：

[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China

[2] Minist Educ, Key Lab Adv Reactor Engn & Safety, Beijing 100084, Peoples R China

来源：

PROGRESS IN NUCLEAR ENERGY | 2014年 / 77卷

基金：

中国国家自然科学基金;

关键词：

Fission products; Graphite dust; Deposition; HTGR; REACTOR;

D O I：

10.1016/j.pnucene.2014.04.016

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

A High Temperature Helium Experimental Loop (HTHEL) for the purpose of studying the transportation and deposition behavior of solid fission products in high-temperature helium coming from the steam generator (SG) in the 10 MW High Temperature Gas-cooled Test Reactor (HTR-10) is studied and designed. Through the optimal design based on thermohydraulics analysis, the three-sleeve structure of deposition sampling device (DSD) could realize full-length temperature control evenly and simulate the physical environment of the heat transfer tube of SG in the HTR-10 in the sense of thermohydraulics, which could be used to study the original source term in the primary circuit. The simulation of the graphite dust particle trajectories in the DSD are shown and it is elucidated that DSD could also be used to study the behavior of graphite dust in the high temperature helium in the SG of HTR, which will provide deeper understanding for the analysis of source terms of HTR-10. (C) 2014 Elsevier Ltd. All rights reserved.

引用

页码：329 / 335

页数：7

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