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|
Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor
1 Advanced Nuclear Systems Institute, Belgian Nuclear Research Centre SCK•CEN, Mol, Belgium
2 Nuclear Fission Division, CIEMAT, Madrid, Spain
a e-mail: email@example.com
Published online: 13 September 2017
VENUS-F is a fast, zero-power reactor with 30% wt. metallic uranium fuel and solid lead as coolant simulator. It serves as a mockup of the MYRRHA reactor core. This paper describes integral experiments performed in two critical VENUS-F core configurations (with and without graphite reflector). Discrepancies between experiments and Monte Carlo calculations (MCNP5) of keff, fission rate spatial distribution and reactivity effects (lead void and fuel Doppler) depending on a nuclear data library used (JENDL-4.0, ENDF-B-VII.1, JEFF-3.1.2, 3.2, 3.3T2) are presented.
© 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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