VENUS-F is a fast, zero-power reactor with 30% wt. metallic uranium fuel and solid lead ascoolant 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.
|Title of host publication||EPJ Web of Conferences|
|Subtitle of host publication||ND 2016: International Conference on Nuclear Data for Science and Technology|
|Number of pages||4|
|State||Published - 13 Sep 2017|
|Name||EPJ Web of Conferences|