Venus-2 Mox fuelled Reactor Dosimetry Calculations

Nadia Messaoudi, Byung-chan NA, Da Ruan

    Research outputpeer-review


    The OECD/NEA Nuclear Science Committee organised the two-dimensional VENUS-1 and the three-dimensional VENUS-3 international intercomparison exercises to examine current state-of-the-art computation methods of calculating neutron flux to reactor components. Both benchmarks dealt with UO2-fuelled systems and were completed in 2000. The analysis of results revealed that 3-D neutron fluence calculations provide results that are significantly more accurate that those obtained from 2 D calculations and further demonstrated that performing 3-D calculations is technically feasible given the power of today’s computers. As a follow-up to the previous benchmarks and with the knowledge that the use of MOX fuel in LWRs presents different neutron characteristics, a three-dimensional VENUS-2 MOX-fuelled reactor dosimetry benchmark was launched, in 2004, based on experimental data released by SCK•CEN, Mol, Belgium. Twelve participants contributed to this benchmark, providing 15 solutions. This report provides details of the comparison analysis of calculated results against experimental data.
    Original languageEnglish
    Place of PublicationParis, France
    PublisherOECD NEA - Nuclear Energy Agency
    Number of pages227
    ISBN (Print)978-92-64-01084-0
    StatePublished - Mar 2006

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