Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR)
Data(s) |
01/10/2014
31/12/1969
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Resumo |
This paper presents an assessment analysis of damage domains of the 30 MWth prototype High-Temperature Engineering Test Reactor (HTTR) operated by the 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 conditions are presented and compared with those obtained by the JAEA. |
Formato |
application/pdf |
Identificador | |
Idioma(s) |
eng |
Publicador |
E.T.S.I. Industriales (UPM) |
Relação |
http://oa.upm.es/35674/1/INVE_MEM_2014_181993.pdf http://www.sciencedirect.com/science/article/pii/S0306454914002229 info:eu-repo/semantics/altIdentifier/doi/10.1016/j.anucene.2014.05.008 |
Direitos |
http://creativecommons.org/licenses/by-nc-nd/3.0/es/ info:eu-repo/semantics/embargoedAccess |
Fonte |
Annals of Nuclear Energy, ISSN 0306-4549, 2014-10, Vol. 72, No. null |
Palavras-Chave | #Energía Nuclear |
Tipo |
info:eu-repo/semantics/article Artículo PeerReviewed |