Analysis of the reactivity coefficients and fuel burnup for MNSR research reactor using DRAGON5/DONJON5 codes
Author:
Publisher
Elsevier BV
Subject
Radiation
Reference31 articles.
1. Validation of DRAGON4/DONJON4 simulation methodology for a typical MNSR by calculating reactivity feedback coefficient and neutron flux;Al Zain;Results Phys.,2018
2. Calculation of the effect of boron as impurity on the reactivity of the miniature neutron source reactors using the MCNP code;Albarhoum;Prog. Nucl. Energy,2015
3. Investigative studies on the effects of cadmium rabbits on high enriched uranium-fueled and low enriched uranium-fueled cores of ghana research reactor-1 using MCNP5 code;Boffie;Nucl. Eng. Des.,2013
4. CIAE, 1993. Safety analysis report (SAR) for the Syrian Miniature Neutron Source Reactor, China.
5. ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data;Chadwick;Nuclear Data Sheets,2011
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1. Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (T-H) characteristics of the MNSR research reactor fuel assembly;Nuclear Engineering and Design;2024-01
2. Negative temperature coefficients of reactivity for metallic fuel Dual Fluid Reactor;Progress in Nuclear Energy;2022-04
3. Safety analysis TMSR-500 in terms of the temperature reactivity coefficient of the fuel and the moderator using the MCNP6 software;Journal of Physics: Conference Series;2021-05-01
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