Published October 2014 | Version v1
Journal article

Simulation of HTR-10 helium circulator trip test

  • 1. Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing (China)

Description

The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first module high temperature gas-cooled reactor in China. The helium circulator trip test is one of the commissioning tests conducted on the HTR-10. This test not only verifies the safety features of the HTR-10 after the loss of forced cooling condition, but also provides the measured data for the validation of system analysis codes. Based on the actual test conditions, the helium circulator trip test was simulated using the THERMIX code. Furthermore, main reactor parameters of interest were analyzed. The calculated reactor power agrees well with the test one, thus the validity, reasonability and applicability of THERMIX are fully demonstrated. During the test process, the maximum fuel center temperature is always below its limit value of 1230 ℃. (authors)

Additional details

Publishing Information

Journal Title
Atomic Energy Science and Technology
Journal Volume
48
Journal Issue
suppl
Journal Page Range
p. 218-221
ISSN
1000-6931

Optional Information

Notes
6 figs., 1 tab., 5 refs.