Comparative study on neutron data in integral experiments of MYRRHA mockup critical cores in the VENUS-F reactor

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Institutes & Expert groups

  • CIEMAT - Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas

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Abstract

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.

Details

Original languageEnglish
Title of host publicationEPJ Web of Conferences
Subtitle of host publicationND 2016: International Conference on Nuclear Data for Science and Technology
Pages1-4
Number of pages4
Volume146
Edition2017
DOIs
Publication statusPublished - 13 Sep 2017

Publication series

NameEPJ Web of Conferences
PublisherEDP Sciences
ISSN (Print)2100-014X

Keywords

  • VENUS-F, MYRRHA, Monte Carlo, lead void, nuclear data library, fast neutron, MCNP, fuel Doppler, reactivity effects

ID: 6776099