Title of article
Thermal hydraulic instrumentation system of the HTR-10 Original Research Article
Author/Authors
Zhong Shuoping، نويسنده , , Hu Shouyin، نويسنده , , Zha Meisheng، نويسنده , , Li Shengqiang، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2002
Pages
10
From page
199
To page
208
Abstract
The 10 MW high temperature gas-cooled reactor—test module (HTR-10) has many different characteristics compared with the pressure water reactor (PWR), such as special fuel elements, core construction, helium coolant and so on. Thus, the design of thermal hydraulic instrumentation system of the HTR-10 is also different from that of a PWR. This paper describes the design criteria and system integrating method of thermal hydraulic instrumentation systems in details. The main thermal instrumentation and devices specially developed for the HTR-10 are also introduced.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2002
Journal title
Nuclear Engineering and Design Eslah
Record number
889623
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