Open AccessSome questions on nuclear safety of heavy-water power reactor operating in self-sufficient thorium cycle
Author(s) -
B. R. Bergel’son,
А. С. Герасимов,
G. V. Tikhomirov
Publication year - 2008
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp0802022b
Subject(s) - nuclear engineering , coolant , heavy water , nuclear reactor , research reactor , power density , void (composites) , environmental science , materials science , nuclear power , nuclear physics , power (physics) , neutron , physics , thermodynamics , engineering , composite material , deuterium
In this paper the comparative calculations of the void coefficient have been made for different types of channel reactors for the coolant density interval 0.8-0.01 g/cm3. These results demonstrate the following. In heavy-water channel reactors, the replacement of D2O coolant by H2O, ensuring significant economic advantage, leads to the essential reducing of nuclear safety of an installation. The comparison of different reactors by the void coefficient demonstrates that at the dehydration of channels the reactivity increase is minimal for HWPR(Th), operating in the self-sufficient mode. The reduction of coolant density in channels in most cases is accompanied by the increase of power and temperatures of fuel assemblies. The calculations show that the reduction of reactivity due to Doppler effect can compensate the effect of dehydration of a channel. However, the result depends on the time dependency of heat-hydraulic processes, occurring in reactor channels in the specific accident. The result obtained in the paper confirms that nuclear safety of HWPR(Th) lies on the same level as nuclear safety of CANDU type reactors approved in practice