SYMPOSIA PAPER Published: 01 January 2007
STP45428S

Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System

Source

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 27AI(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.

Author Information

Kim, Do, Heon
Korea Atomic Energy Research Institute, Yuseong, Daejeon, Korea
Gil, Choong-Sup
Korea Atomic Energy Research Institute, Yuseong, Daejeon, Korea
Chang, Jonghwa
Korea Atomic Energy Research Institute, Yuseong, Daejeon, Korea
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Details
Developed by Committee: E10
Pages: 77–84
DOI: 10.1520/STP45428S
ISBN-EB: 978-0-8031-6242-6
ISBN-13: 978-0-8031-3412-6