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Assessment of damage domains of the High-Temperature Engineering Test Reactor (HTTR)
Citation
Flores Flores, Alain, Izquierdo Rocha, José María, Tuček, Kamil and Gallego Díaz, Eduardo F. 
ORCID: https://orcid.org/0000-0001-8338-4959
(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) |
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| Author/s: |
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| 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 |
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: | https://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/S... |
| Deposited by: | Memoria Investigacion |
| Deposited on: | 22 Sep 2015 16:44 |
| Last Modified: | 31 Oct 2018 23:30 |
