Safety analysis of reactivity insertion accidents in a heavy water nuclear research reactor core using coupled 3D neutron kinetics thermal-hydraulic system code technique

Author:

Titouche Kouidri W.,Letaim F.,Boucenna A.,Boulhaouchet M.H.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference24 articles.

1. A general description of the code WIMS;Askrew;J. Br. Nucl. Energy Soc.,1966

2. Steady-state thermal hydraulic analysis of the equilibrium core of Pakistan research reactor-1;Bokhari;Ann. Nucl. Energy,2007

3. Analyse thermohydraulic du tube de precédé par le code RELAP5/Mod3.2;Boulhaouchet,2003

4. Analysis of reactivity insertion transient experiments in a nuclear research reactor core and comparison with RETRAC-PC computational results;Bousbia-Salah;Alg. Rev. Nucl. Sci.,2001

5. Overview of Coupled System Thermal Hyraulique-3D Neutron Kinetics Code Applications;Bousbia-Salah,2004

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