Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core

Author:

Adorni Martina,Bousbia-Salah Anis,Hamidouche Tewfik,Maro Beniamino Di,Pierro Franco,D’Auria Francesco

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference10 articles.

1. Analysis of the IAEA research reactor benchmark problem by the RETRAC-PC code;Bousbia Salah;Nuclear Engineering and Design,2005

2. D’Auria et al., 2004. Neutronics/Thermal-hydraulics Coupling in LWR Technology, vol. 2, State of the Art Report. OECD 2004, NEA No. 5436.

3. Di Maro, B., Pierro, F., Adorni, M., Bousbia-Salah, A., D’Auria, F., 2003. Safety analysis of loss of flow transients in a typical research reactor by RELAP5/MOD3.3. In: Proc. Int. Conference nuclear energy for new Europe 2003, Portorož, Slovenia.

4. Dynamic calculations of the IAEA safety MTR research reactor benchmark problem using RELAP5/3.2 code;Hamidouche;Annals of Nuclear Energy,2004

5. IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uranium fuels Guidebook.

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