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 proceedings › In-proceedings paper
Institutes & Expert groups
- CIEMAT - Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
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DOI
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 language | English |
|---|---|
| Title of host publication | EPJ Web of Conferences |
| Subtitle of host publication | ND 2016: International Conference on Nuclear Data for Science and Technology |
| Pages | 1-4 |
| Number of pages | 4 |
| Volume | 146 |
| Edition | 2017 |
| DOIs | |
| Publication status | Published - 13 Sep 2017 |
Publication series
| Name | EPJ Web of Conferences |
|---|---|
| Publisher | EDP 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