Full-scale modelling of the MNSR reactor to simulate normal operation, transients and reactivity insertion accidents under natural circulation conditions using the thermal hydraulic code ATHLET-Reference-Cited by-同舟云学术

Full-scale modelling of the MNSR reactor to simulate normal operation, transients and reactivity insertion accidents under natural circulation conditions using the thermal hydraulic code ATHLET

Published:2005-01 Issue:1 Volume:235 Page:33-52
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hainoun A.,Alissa S.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. Conceptual design loss-of-coolant accident analysis for the advanced neutron source reactors;Chen;Nucl. Technol.,1994

2. Hainoun, A., 1994. Modellierung des unterkühlten Siedens in ATHLET und Anwendung in wassergekühlten Forschungsreaktoren, D 294 Diss. Uni. Bochum, Jül-2961.

3. Modelling of void formation in the subcooled boiling regime in the ATHLET code to simulate flow instability for research reactors;Hainoun;Nucl. Eng. Des.,1996

4. Determination of neutron generation time in MNSR reactor by measurement of neutronics transfer function;Hainoun;NED,2000

5. Sets of experiments in nuclear engineering associated with the Syrian MNSR;Khamis;AECS-PH/RSS,1999

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