Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR)
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.
FLORES Y FLORES Alain;
IZQUIERDO Jose Maria;
TUCEK Kamil;
GALLEGO Eduardo;
2014-07-02
PERGAMON-ELSEVIER SCIENCE LTD
JRC86012
0306-4549,
http://www.sciencedirect.com/science/article/pii/S0306454914002229,
https://publications.jrc.ec.europa.eu/repository/handle/JRC86012,
10.1016/j.anucene.2014.05.008,
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