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Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System Pages: 8 Published: Jan 2007
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View License Agreement Source: STP1490-EB Abstract The benchmark calculation for the 3-D VENUS-2 MOX-fueled reactor dosimetry has been performed by the TRANSX/DANTSYS code system. The nuclear data from the ENDF/B-VI.8, JENDL-3.3, and JEFF-3.0 have been processed for the MATXS-format 199-group neutron libraries by NJOY99.90. The equivalent fission fluxes at the 34 measurement positions on the core mid-plane have been calculated using the dosimetry reaction rates for the Ni(), In(), Rh(), Zn(), Np(), and AI() detectors. The estimated results by the JENDL-3.3 and JEFF-3.0 have been compared with those by the ENDF/B-VI.8.
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