Thermalhydraulic investigation using a test facility simulating 200 MW integral heating reactor

Citation
Hj. Jia et al., Thermalhydraulic investigation using a test facility simulating 200 MW integral heating reactor, J NUC SCI T, 37(2), 2000, pp. 202-208
Citations number
8
Categorie Soggetti
Nuclear Emgineering
Journal title
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
ISSN journal
00223131 → ACNP
Volume
37
Issue
2
Year of publication
2000
Pages
202 - 208
Database
ISI
SICI code
0022-3131(200002)37:2<202:TIUATF>2.0.ZU;2-C
Abstract
Since the middle of 1980's, a research program on heating reactor has been carried out at, Institute of Nuclear Energy Technology (INET) of Tsinghua U niversity in China, Chs healing reactor is a light water cooled, integral t ype natural circulation reactor with low system pressure and low core exit quality, it has the passive safety features and other advanced characterist ics of the next generation reactors. Because of a relatively long riser and low system pressure, a small quality perturbation at the exit of the core will lead to a relatively large variation of void fraction in the riser, so will the driving force. All of the above features made it very different from the typical PWRs and BWRs. In order to guarantee the safe operation of the heating reactor, a fu ll scale test loop HRTL-200, simulating HR-200 healing reactors in main geo metry and operation parameters, was constructed and operated under the broa d test conditions covering the 200MW heating reactor operation conditions a t INET. The HRTL-200 test facility, same of steady-state and two-phase flow instability test results from the test facility and the consideration how to choose the optimal design parameters for the heating reactors are shown in this; paper. The range of experimentally studied parameters are: the sys tem pressure is from 1.0 to 4.0 NPa, the largest heat Aux is about 50 W/cm( 2), and the quality at the exit, of the test section is less than 6%.