Burnup Influence on the Neutron Fluence of VVER-1000 Reactor Vessel

Ivaylo Panayotov, Nikolay Mihaylov, Krassimira Ilieva, Desislava Kirilova, Maria Manolova, INRNE-BAS, Bulgaria

19th Symposium of AER on VVER Reactor Physics and Reactor Safety (2009, Varna, Bulgaria)
Physical problems of Spent Fuel, Decommissioning and Radwaste


The neutron fluence of the vessels of the reactors is determined regularly accordingly the RPV Surveillance Program of Kozloduy NPP Unit 5 and 6 in order to assess the state of the metal vessel and their radiation damaging. The calculations are carried out by the method of discrete ordinates used in the TORT program for operated reactor cycles. An average reactor spectrum corresponding to fresh U-235 fuel is used as an input neutron source. The impact of the burn up of the fuel on the neutron fluence of VVER-1000 reactor vessel is evaluated.

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