Volume 3, Issue 3 (March 2006)
Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System
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 58Ni(n,p), 115In(n,n'), 103Rh(n,n'), 64Zn(n,p), 237Np(n,f), and 27Al(n,α) detectors. The estimated results by the JENDL-3.3 and JEFF-3.0 have been compared with those by the ENDF/B-VI.8.