Abstract
Beryllium (Be) is a precious resource with many high value uses, the low energy threshold (n,2n) reaction makes Be an excellent neutron multiplier for use in fusion breeder blankets. Estimates of Be requirements and available resources suggest that this could represent a major supply difficulty for solid-type blanket concepts. Reducing the quantity of Be required by breeder blankets would help to alleviate the problem to some extent. In addition, it is important that the reduction in the Be quantity does not diminish the blanket's performance in key aspects such as the tritium breeding ratio (TBR), energy multiplication and peak nuclear heating.Mixed pebble bed designs allow for the multiplier fraction to be varied throughout the blanket. This neutronics study used MCNP 6 to investigate linear variations of the multiplier fraction in relation to blanket depth, in order to better utilise the important multiplying Be(n,2n) and breeding reactions. Blankets with a uniform multiplier fraction showed little scope for reduction in Be mass. Blankets with varying multiplier fractions were able to simultaneously use 10% less Be, increase the energy amplification by 1%, reduce the peak heating by 7% and maintaining a sufficient TBR when compared to the performance achievable using a uniform composition.
Highlights
The sustainability of resources required for deuterium tritium (DT) fusion have been previously considered [1,2]
Blankets with varying multiplier fractions were able to simultaneously use 10% less Be, increase the energy amplification by 1%, reduce the peak heating by 7% and maintaining a sufficient TBR when compared to the performance achievable using a uniform composition
This paper aims to explore the possibility of decreasing the amount of Be required in mixed bed breeder blanket designs
Summary
The sustainability of resources required for deuterium tritium (DT) fusion have been previously considered [1,2]. The usage of Be in fusion devices is common and is demonstrated by Be being the reference material for solid-type breeder blankets in ITER [3] and beryllides such as Be12Ti are considered a promising neutron multiplier for DEMOnstration power plants (DEMO) [4]. Recycling of irradiated beryllium [5] is one option that could reduce the amount of Be usage over a reactor’s lifetime. Another approach that could be carried out in tandem is to reduce the amount of Be specified in breeder blanket designs. This paper aims to explore the possibility of decreasing the amount of Be required in mixed bed breeder blanket designs
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