Article ID Journal Published Year Pages File Type
1741006 Progress in Nuclear Energy 2012 5 Pages PDF
Abstract
► Neutronic analysis of SPERT IV reactor was performed. ► Combination of WIMS and CITATION was used for core modeling. ► Calculations performed to estimate feed back coefficients, kinetic parameters, neutron flux and control rod worth. ► Calculated values agree with experimental data.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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