Distributions of Nuclides and Pin Powers in ALLEGRO Core

Zajac, Radoslav; VÚJE

25th Symposium of AER on VVER Reactor Physics and Reactor Safety (2015, Balatongyörök, Hungary)
Nuclear fuel Cycle Perspectives and Sustainability


SERPENT 2.1.21 code, continuous-energy Monte Carlo calculation, was used for verificati
on of CEA ALLEGRO reactor concept. ESNII+ 1 international benchmark was a motivation
to evaluate the SERPENT core model. The position of control devices was set in the way that
the starting state was equal to the critical state. At burnup of 18.8 MWd/kgHM were evaluated
the power distribution on the assemblies of ALLEGRO reactor core and power distribution on
the pins around CSD rod. In the article is also studied the distribution of some uranus,
transuranus and fission products in the core assemblies at the end of the MOX lifetime. There
are analysed the processes of homogenous transmutation evenly dispersed minor actinides
(MA) in the fuel and heterogeneous transmutation of MA in inert and UO2 matrix located in
the central pin of three assemblies in the zone.

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