Abstract

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 k eff , 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.

Highlights

  • VENUS-F [1] fast, zero-power reactor core was assembled within the GUINEVERE FP6 EC program (2008-2011) [2] at the Belgian Nuclear Research Centre SCKCEN

  • Fast neutron integral experiments were performed on five critical VENUS-F configurations to address the nuclear data needs for the neutronic design of the MYRRHA and ALFRED reactor [5]

  • It consists of 108 fuel assemblies, 6 safety rods, 3 control rods, 4 fast spectrum in-pile sections (IPS), 6 thermal spectrum IPS, and BeO reflector assemblies and dummy assemblies filled with lead-bismuth eutectic (LBE)

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Summary

Introduction

VENUS-F [1] fast, zero-power reactor core was assembled within the GUINEVERE FP6 EC program (2008-2011) [2] at the Belgian Nuclear Research Centre SCKCEN. The main aims were to validate online reactivity monitoring techniques and nuclear data for MYRRHA [4], which will be a fast ADS demonstrator with the option to be operated in a critical mode. Fast neutron integral experiments were performed on five critical VENUS-F configurations to address (part of) the nuclear data needs for the neutronic design of the MYRRHA and ALFRED reactor [5]. The VENUSF critical cores were thoroughly characterized and the following parameters were measured:. Several selected parameters measured in two of the critical VENUS-F configurations are compared with MCNP5 calculations using general-purpose nuclear data libraries (JEFF, ENDF-B, JENDL). A detailed analysis of spectral index measurements performed in all VENUS-F critical cores is presented in another article of these proceedings [6]

MYRRHA mockup cores in VENUS-F
Computational tools
Effective multiplication factor
Radial fission rate distribution
Lead coolant void reactivity effect
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