RADIOACTIVE RELEASE AND DOSE CALCULATIONS FOR THE HTR-10

Authors
Citation
Yz. Liu, RADIOACTIVE RELEASE AND DOSE CALCULATIONS FOR THE HTR-10, Nuclear technology, 124(2), 1998, pp. 192-197
Citations number
5
Categorie Soggetti
Nuclear Sciences & Tecnology
Journal title
ISSN journal
00295450
Volume
124
Issue
2
Year of publication
1998
Pages
192 - 197
Database
ISI
SICI code
0029-5450(1998)124:2<192:RRADCF>2.0.ZU;2-M
Abstract
A 10-MW high-temperature gas-cooled test reactor; the High-Temperature Reactor-10 (HTR-10), being built at the Institute of Nuclear Energy T echnology of Tsinghua University, is re type of modular high-temperatu re gas-cooled reactor The design features of the HTR-10 are studied in terms of five important sources Of airborne radioactive materials rel eased to the environment. These sources are activation of the air in t he reactor cavity, leakage of the primary coolant, release of radioact ively contaminated helium from the regeneration of the helium purifica tion systems, release of radioactively contaminated helium from the ga s evacuation subsystem of the fuel load and unload systems, and leakag e of the vapor from the water/steam loops. On the basis of the HTR-10 design parameters, the amount of radioactivity released to the environ ment per year is calculated, and the dose to the public is calculated as it relates to the HTR-10 site.