Home / Publications / Journals / Nuclear Technology / Volume 91 / Number 2
Nuclear Technology / Volume 91 / Number 2 / August 1990 / Pages 247-258
Technical Paper / Safety of Next Generation Power Reactor / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34432
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The short-term thermal response of the Modular High-Temperature Gas-Cooled Reactor is analyzed for a range of flow and reactivity transients. These include loss of forced circulation without scram, moisture ingress, spurious withdrawal of a control rod group, hypothetical large and rapid positive reactivity insertion, and a rapid core cooling event. The coupled heat transfer-neutron kinetics model is also described.