Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code

Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code

Cases of core coolant flow blockage transient have been simulated and analysed for the TRIGA IPR-R1 research reactor using the RELAP5-MOD3.3 code. The transients are related to partial and to total obstruction of the core coolant channels. The reactor behaviour after the loss of flow was analysed as...

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Bibliographic Details
Main Authors: Patrícia A. L. Reis, Antonella L. Costa, Claubia Pereira, Maria Auxiliadora F. Veloso, Amir Z. Mesquita
Format: Article
Language:English
Published: Wiley 2015-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2015/354163
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