Authors & Affiliations

Zhdanov V.S.1, Mosunova N.A.2, Pribaturin N.A.1, Strizhov V.F.2, Usov E.V.1
1 Nuclear Safety Institute of the Russian Academy of Sciences, Novosibirsk Branch, Novosibirsk, Russia
2 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, Russia

Zhdanov V.S. – Head of laboratory, Cand. Sci. (Tech.), Novosibirsk Branch, Nuclear Safety Institute of the Russian Academy of Sciences.
Mosunova N.A. – Head of Department, Cand. Sci. (Phys.-Math.), Nuclear Safety Institute of the Russian Academy of Sciences.
Pribaturin N.A. – Dr. Sci. (Tech.), Head of Novosibirsk Branch, Nuclear Safety Institute of the Russian Academy of Sciences.
Strizhov V.F. – Deputy director, Dr. Sci. (Phys.-Math.), Nuclear Safety Institute of the Russian Academy of Sciences.
Usov E.V. – Head of laboratory, Cand. Sci. (Tech.), Novosibirsk Branch, Nuclear Safety Institute of the Russian Academy of Sciences. Contacts: 1, Lavrenteva str., Novosibirsk, Russia, 630090. Tel.: +7 (962) 834-29-34; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

The analysis of the published experimental data on modelling of accidental situations with destruction and melting of core components of fast neutrons reactors with liquid metal coolant for the analysis of fuel pins and fuel assemblies (FA) behaviour in the conditions of severe accidents with such initial events, as FA full instant blockage, uncontrolled loss of the coolant flow (ULOF) or uncontrolled overtop of reactor power (UTOP) is presented. In-pile and out-of-pile experiments, results of measurements of parameters of experiments and post-experimental researches are considered.
Integral codes used at all design stages use results of experimental modelling of the phenomena occurring in reactor facilities both during normal operation, and in the conditions of incidents and severe accidents. Extensive experimental researches in 1970-1995 now have restarted in the several countries in connection with announcement of programs of the closed fuel cycle.
The analysis of a experimental database condition of shows that modern development of new fuel types, a material of fuel pins cladding and as a whole fuel pin designs demand refinement of experimental data, and also obtaining new data, for correct verification of integral codes.

Keywords
fast neutron reactor, liquid metal coolant, experimental research, severe accident, initial events, fuel rod, FA blockage, loss of flow, reactivity overtop, melting of cladding, melting of fuel, melt relocation, hexcan damage, interaction with coolant

Article Text (PDF, in Russian)

References

UDC 621.039.586

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, issue 1, 1:19