Abstract
A target accuracy assessment of the effective neutron multiplication factor, keff, for MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) lead-bismuth cooled fast reactor has been performed with JEFF-3.3 and ENDF/B-VIII.0 state-of-the-art nuclear data libraries and the SUMMON system. Uncertainties in keff due to uncertainties in nuclear data have been assessed against the target accuracies provided by SG-26 of the WPEC of OECD/NEA in 2008 for LFR. Results show that keff target accuracy is still exceeded by more than a factor of two using the latest nuclear data evaluations released in 2018. Consequently, nuclear data assimilation has been carried out using criticality experiments from the International Criticality Safety Benchmark Evaluation Project that are representative of MYRRHA. The results from this work show that the level of accuracy needed in nuclear data cannot be obtained using only differential experiments, but the combination of experimental covariance data and integral experiments together with Generalised Least Squares technique can provide adjusted nuclear data capable of predicting reactor properties with lower uncertainty and consistent with differential data.
Highlights
The Lead-cooled Fast Reactor (LFR) is one of the three technologies selected by the Sustainable Nuclear Energy Technology Platform (SNETP) [1] that can meet future European energy needs
A target accuracy assessment of the effective neutron multiplication factor, keff, for MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) [4] lead-bismuth cooled fast reactor is performed with the JEFF-3.3 [5] and ENDF/B-VIII.0 [6] state-of-the-art nuclear data libraries and the Sensitivity and Uncertainty Methodology for MONtecarlo codes (SUMMON) system [7]
A target accuracy assessment of the effective neutron multiplication factor for MYRRHA innovative lead-bismuth cooled fast reactor has been carried out using the JEFF-3.3 and ENDF/B-VIII.0 state-of-the-art nuclear data libraries and the SUMMON system
Summary
The Lead-cooled Fast Reactor (LFR) is one of the three technologies selected by the Sustainable Nuclear Energy Technology Platform (SNETP) [1] that can meet future European energy needs. Significant efforts are being made by researchers and industry to overcome the main drawbacks for the industrial deployment of LFR, which are the lack of operational experience and the impact of uncertainties in the reactor design, operation and safety assessment. A target accuracy assessment of the effective neutron multiplication factor, keff, for MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) [4] lead-bismuth cooled fast reactor is performed with the JEFF-3.3 [5] and ENDF/B-VIII.0 [6] state-of-the-art nuclear data libraries and the SUMMON system [7]. Uncertainty quantification (UQ) analyses have already been carried out for previous MYRRHA designs [8-10] or with older nuclear data evaluations [11]; since JEFF-3.3 and ENDF/B.VIII.0 were released, an updated analysis was required in order to take into account the changes in the new nuclear data libraries and their impact in the criticality safety coefficients. Data assimilation for the main isotopes contributing to the uncertainty has been performed using critical mass experiments from the International Criticality Safety Benchmark Evaluation Project (ICSBEP) [12] that are representative of MYRRHA, in order to obtain adjusted nuclear data with constrained uncertainties and to reduce the uncertainty in the criticality parameter
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