Abstract
Two approaches have been considered in France by the CAPRA team to optimise a fast reactor for plutonium (or minor actinide) burning : the “dilution” and “poisoning” options /l/. At present, “dilution” is the preferred design as it allows better core safety parameters (mainly the Doppler constant). This paper shows a route, based on the use of a moderator material, 11B4C, to improve the core safety parameters (Doppler constant and sodium void reactivity worth) of the CAPRA B4C poisoned core. The aim is to obtain a convincing alternative to the “dilution” option. The introduction of the moderator inside the fuel bundle of the CAPRA B& poisoned core allows to strongly increase the Doppler constant (+ 62 %) and to reduce the sodium void reactivity worth (- 23 %). The “poisoned” CAPRA core with “B4C has similar plutonium burning performances and better core safety parameters than the “dilution” option. Its main advantages are linked to the larger diameter fuel pins: increased fuel lifetime and “standard” fuel bundle (397 pins instead of 469).
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