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

Flores Flores, Alain and Izquierdo Rocha, José María and Tuček, Kamil and Gallego Díaz, Eduardo F. (2014). Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR). "Annals of Nuclear Energy", v. 72 (n. null); pp. 242-256. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2014.05.008.

Description

Title: Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR)
Author/s:
  • Flores Flores, Alain
  • Izquierdo Rocha, José María
  • Tuček, Kamil
  • Gallego Díaz, Eduardo F.
Item Type: Article
Título de Revista/Publicación: Annals of Nuclear Energy
Date: October 2014
ISSN: 0306-4549
Volume: 72
Subjects:
Freetext Keywords: HTTR; Dynamic reliability; Modelling; High temperature gas cooled reactor; Simulation; Damage domain
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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.

More information

Item ID: 35674
DC Identifier: http://oa.upm.es/35674/
OAI Identifier: oai:oa.upm.es:35674
DOI: 10.1016/j.anucene.2014.05.008
Official URL: http://www.sciencedirect.com/science/article/pii/S0306454914002229
Deposited by: Memoria Investigacion
Deposited on: 22 Sep 2015 16:44
Last Modified: 31 Oct 2018 23:30
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