Published May 2019 | Version v1
Miscellaneous Metadata-only

Numerical investigation of the fuel cladding disruption in contact with the molten metallic fuel of a sodium-cooled fast reactor

Creators

  • 1. Nuclear Safety Institute of the Russian Academy of Sciences, Novosibirsk (Russian Federation)
  • 2. Kutateladze Institute of Thermophysics, Siberian Branch of the Russian Academy of Sciences, Novosibirsk (Russian Federation)

Description

This paper presents the results of a simulated experiment on the disruption of fuel cladding due to its interaction with molten metallic uranium fuel. The system of mass, energy, and momentum conservation equations is solved accounting for heat transfer between molten fuel and the fuel cladding, heat transfer between the fuel rod and the coolant (liquid sodium), and the melting of the fuel cladding. Also a thermal problem with the melting of the fuel cladding is solved. The calculation yields data on the distinctive features of failure of fuel rods with metallic fuel, the characteristic failure times of the fuel cladding, and the interaction of molten metallic fuel with liquid sodium. (author)

Part of:
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)

Additional details

Publishing Information

Imprint Title
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
Imprint Pagination
[4028 p.]
Journal Page Range
5 p.

Conference

Title
27. international conference on nuclear engineering
Acronym
ICONE-27
Dates
19-24 May 2019
Place
Tsukuba, Ibaraki (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
51012940
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
E CODES; FILM FLOW; FUEL-CLADDING INTERACTIONS; HEAT TRANSFER; MELTDOWN; MOLTEN SALT FUELS; NEUTRON PHYSICS; PRESSURE DROP; S CODES; SODIUM COOLED REACTORS; THERMAL CONDUCTIVITY; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; ENERGY SOURCES; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; FUELS; HYDRAULICS; LIQUID FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; MECHANICS; NUCLEAR FUELS; PHYSICAL PROPERTIES; PHYSICS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SEVERE ACCIDENTS; THERMODYNAMIC PROPERTIES

Optional Information

Notes
Available as Internet Data in PDF format, Folder Name: Track08, Paper ID: ICONE27-1707F.pdf; 4 refs., 8 figs., 2 tabs.