HTGR Knowledge Base
Conference Article: Test apparatus of cooling panel system for MHTGR
Takada, S.; Suzuki, K.; Inagaki, Y.; Miyamoto, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of High Temperature Engineering)Abstract
A test apparatus of cooling panel system is provided to investigate heat removal performance and temperature distribution of reactor pressure vessel. The test apparatus consists of a test section and systems for water supply, helium gas supply, vacuum and instrumentation and control. The test section is composed of pressure vessel (1000mm in diameter, 3000mm in height) containing an electric heater (max. 100kw, 600 deg. C) which simulates a reactor core and cooling panels surrounding the pressure vessel. Helium and argon gas are used and gas pressure is varied from vacuum to 1.0MPa in the pressure vessel. In the test, temperature distribution of the components in the test section, helium gas temperature, heat flux removed from the electric heater and heat flux transferred to the cooling panels are acquired.
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key words: Gas Cooled Reactor, Nuclear Technology
- Reference:
- Specialists meeting on decay heat removal and heat transfer under normal and
accident conditions in gas cooled reactors. Juelich (Germany). 6-8 Jul 1992
- International Atomic Energy Agency, Vienna (Austria)
- IAEA-TECDOC--757, pp:147-151
- International Atomic Energy Agency, Vienna (Austria)