Abstract
The advantages of ADS with subcritical reactor cooled by lead are discussed from safety point of view in contrast to critical systems. There is good reason to believe that the most severe accidents are impossible in the ADS. In the frames of IAEA neutronic benchmark the reactivity and burn-up simulation have been done: fuel enrichment and external neutron source intensity needed to keep constant power during life-time have been calculated. Reactivity effects (void and removing the fission products) are determined. We have shown that constant uncertainties may result in life-time duration dramatically. The detailed data on power and spectral index distribution have been calculated. The most of calculations were performed using diffusion code RZA and Monte-Carlo code MMFK. The formalism of K, have been discussed and special modules for source and K s simulations have been included in RZA code. Constant system was ABBN.
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