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


Autoria(s): Flores Flores, Alain; Izquierdo Rocha, José María; Tuček, Kamil; Gallego Díaz, Eduardo F.
Data(s)

01/10/2014

31/12/1969

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

http://oa.upm.es/35674/

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