Abstract
Integral experiments for nuclear data validation have been carried out at the fast
zero-power reactor VENUS-F at the Belgian Nuclear Research Centre SCKCEN
since 2011. VENUS-F serves as a mock-up of MYRRHA, a fast, lead-bismuth
cooled reactor/accelerator-driven system. First, solid lead was used as a coolant
simulator and reflector at VENUS-F. In 2016, all lead in VENUS-F fuel assemblies
was replaced by bismuth (in total, 625 kg), and a new experimental campaign
was carried out with the aim of validating bismuth properties in integral
experiments, mainly in the neutron energy region from 1 keV up to 10 MeV. Since
2017, lead and bismuth have been combined in fuel assemblies to simulate lead bismuth
eutectic. An overview of the integral experiments is presented in this
paper. Fission rate spatial distributions are compared with Monte Carlo
calculations using various nuclear data libraries. The importance of accurate
knowledge of material composition is discussed using high-purity bismuth samples (99.99 %) as examples. These were characterized by neutron activation
analysis at SCKCEN, mass spectrometry by the supplier (EVOCHEM), and
neutron resonance capture analysis at the GELINA facility of the European
Commission Joint Research Centre.
Original language | English |
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Title of host publication | Reactor Dosimetry: 16th International Symposium |
Subtitle of host publication | ASTM STP 1608 |
Publisher | ASTM International |
Pages | 286-295 |
Number of pages | 10 |
Edition | E10.05 |
DOIs | |
State | Published - 19 Nov 2018 |