HTTRを用いた安全性実証試験における高温二重管内の過渡熱流動解析(原子炉伝熱流動解析の革新(3),原子炉伝熱流動解析の革新)

概要

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Safety demonstration tests using the HTTR are now underway in order to verify the inherent safety features and to improve the safety design and evaluation technologies for HTGRs, as well as to contribute to research and development for VHTR which is one of the Generation IV Reactor candidates. In the safety demonstration tests, a coolant flow reduction test by tripping of all the three gas circulators is planned. A three-dimensional transient numerical-model was produced in order to simulate the thermal-hydraulics between the structure and helium gas in the primary concentric hot gas duct during the coolant flow reduction test. The validity of this model was confirmed by the comparison of the analytical result and the actual transient data from the test of a reactor-scram due to loss of electric-power.
2004-09-04