Abstract
The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical (accelerator driven) and critical modes. One of the key issues for the safe operation of the reactor is the uncertainty assessment during the design works. The main objective of the European project CHANDA (solving CHAllenges in Nuclear DAta) Work Package 10 is to improve MYRRHA relevant nuclear data in order to reduce the reactor parameter uncertainties derived from them. In order to achieve this goal, several tasks have been undertaken. First, a sensitivity study of MYRRHA integral parameters, such as energy dependent cross sections, fission spectra and neutron multiplicities, to nuclear data has been conducted resulting in a list of MYRRHA relevant quantities (nuclides and reactions). On the second task, an analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out. In this framework, the impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model. As the next step, new experiments and evaluations will be performed in order to improve existing nuclear data libraries.
Highlights
MYRRHA is a flexible experimental facility being designed at SCKCEN, Mol, Belgium [1]
The MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) concept is a flexible experimental lead-bismuth cooled and mixed-oxide (MOX) fueled fast spectrum facility designed to operate both in sub-critical and critical modes
The impact on the multiplication factor of quantities from different nuclear data libraries for different nuclides, reactions and energy regions has been investigated on the MYRRHA MOX critical core model
Summary
MYRRHA is a flexible experimental facility being designed at SCKCEN, Mol, Belgium [1]. In the neutronic and safety design of the reactor, an important aspect is the uncertainty propagation and sensitivity to nuclear data; accurate and reliable nuclear data are needed for MYRRHA. Within this framework, a neutron-induced nuclear data sensitivity and uncertainty (S/U) analysis of the latest MYRRHA design has been performed as a first task and a list of the most important nuclides and quantities has been obtained. A detailed analysis of the existing experimental data and evaluations for the quantities included in the list has been carried out, investigating the impact on kef f of quantities from different existing nuclear data libraries for different nuclides, reactions and energy regions on the MYRRHA MOX critical core model.
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