EPJ Web Conf.
Volume 146, 2017ND 2016: International Conference on Nuclear Data for Science and Technology
|Number of page(s)||4|
|Section||Integral Experiments, Benchmarks and Data Validation|
|Published online||13 September 2017|
Analysis of C/E results of fission rate ratio measurements in several fast lead VENUS-F cores
1 Belgian Nuclear Research Centre SCK·CEN, Advanced Nuclear Systems Institute, 2400 Mol, Belgium
2 CIEMAT, Madrid, Nuclear Fission Division, Spain
3 ENEA CASACCIA, Energy and Sustainable Economic Development, Roma, Italy
4 ANSALDO NUCLEARE, S.p.A, Genova, Italy
5 HZDR, Helmholtz-Zentrum Dresden-Rossendorf, Germany
6 ENEA UTFISSM-PRONOC, Energy and Sustainable Economic Development, Saluggia (VC), Italy
a e-mail: firstname.lastname@example.org
Published online: 13 September 2017
During the GUINEVERE FP6 European project (2006–2011), the zero-power VENUS water-moderated reactor was modified into VENUS-F, a mock-up of a lead cooled fast spectrum system with solid components that can be operated in both critical and subcritical mode. The Fast Reactor Experiments for hybrid Applications (FREYA) FP7 project was launched in 2011 to support the designs of the MYRRHA Accelerator Driven System (ADS) and the ALFRED Lead Fast Reactor (LFR). Three VENUS-F critical core configurations, simulating the complex MYRRHA core design and one configuration devoted to the LFR ALFRED core conditions were investigated in 2015. The MYRRHA related cores simulated step by step design peculiarities like the BeO reflector and in pile sections. For all of these cores the fuel assemblies were of a simple design consisting of 30% enriched metallic uranium, lead rodlets to simulate the coolant and Al2O3 rodlets to simulate the oxide fuel. Fission rate ratios of minor actinides such as Np-237, Am-241 as well as Pu-239, Pu-240, Pu-242 and U-238 to U-235 were measured in these VENUS-F critical assemblies with small fission chambers in specially designed locations, to determine the spectral indices in the different neutron spectrum conditions. The measurements have been analyzed using advanced computational tools including deterministic and stochastic codes and different nuclear data sets like JEFF-3.1, JEFF-3.2, ENDF/B7.1 and JENDL-4.0. The analysis of the C/E discrepancies will help to improve the nuclear data in the specific energy region of fast neutron reactor spectra.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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