REVIEW OF EXPERIMENTAL PROGRAMS ON RESEARCH OF FUSION OF ELEMENTS OF FAST REACTORS CORES COMPONENTS IN ACCIDENTAL CONDITIONS-Reference-Cited by-同舟云学术

REVIEW OF EXPERIMENTAL PROGRAMS ON RESEARCH OF FUSION OF ELEMENTS OF FAST REACTORS CORES COMPONENTS IN ACCIDENTAL CONDITIONS

Published:2019-03-26 Issue:1 Volume:2019 Page:238-249
ISSN:2414-1038
Container-title:PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS
language:en
Short-container-title:

Author:

Zhdanov V¹,Mosunova N²,Pribaturin N¹,Strizhov V²,Usov E¹

Affiliation:

1. Novosibirsk Branch, Nuclear Safety Institute of the Russian Academy of Sciences

2. Nuclear Safety Institute of the Russian Academy of Sciences

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.

Publisher

Institute for Physics and Power Engineering (IPPE, Inc.)

Reference27 articles.

1. Proceedings of the International Meeting on Fast Reactor Safety and Related Physics. Chicago, Illinois, 1976. , Proceedings of the International Meeting on Fast Reactor Safety and Related Physics. Chicago, Illinois, 1976.

2. Proceedings of Fourth CSNI Specialist Meeting on Fuel-Coolant Interaction in Nuclear Reactor Safety. Bournemouth, United Kingdom, 1979. , Proceedings of Fourth CSNI Specialist Meeting on Fuel-Coolant Interaction in Nuclear Reactor Safety. Bournemouth, United Kingdom, 1979.

3. Proceedings of the International topical Meeting on Fast Reactor Safety. Knoxville, Tennessee, 1985, vol. 1. , Proceedings of the International topical Meeting on Fast Reactor Safety. Knoxville, Tennessee, 1985, vol. 1.

4. Proceedings of Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors. O-Arai, Ibaraki, JAPAN, 1994. , Proceedings of Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors. O-Arai, Ibaraki, JAPAN, 1994.

5. Experimental Facilities for Sodium Fast reactor Safety Studies. Task Group on Advanced Reactor Experimental Facilities (TAREF). NEA/CSNI/R (2010)12. IRSN 978-92-64-99155-2. , Experimental Facilities for Sodium Fast reactor Safety Studies. Task Group on Advanced Reactor Experimental Facilities (TAREF). NEA/CSNI/R (2010)12. IRSN 978-92-64-99155-2.