JOINT RESEARCH CENTRE

Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR)

Abstract: 
This paper presents assessment analysis of damage domains of the 30 MWth prototype High-Temperature Engineering Test Reactor (HTTR) operated by Japan Atomic Energy Agency (JAEA). For this purpose, an in-house deterministic risk assessment computational tool was developed based on the Theory of Stimulated Dynamics (TSD). To illustrate the methodology and applicability of the developed modelling approach, assessment results of a control rod (CR) withdrawal accident during subcritical condition are presented and compared with those obtained by the JAEA.