Published April 1, 2016 | Version v1
Journal article

Structural-phase state and creep of mixed nitride fuel

  • 1. National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe Highway 31, 115409 Moscow (Russian Federation)

Description

By the analysis of thermal creep data in conjunction with structural-phase state the most likely mechanisms of UN creep are considered. An equation relating the thermal and radiation creep of nitride fuel with such important parameters as plutonium content, porosity, grain size, the content of impurities of transition metals and oxygen, the carbon content has been suggested. At stationary operating parameters in reactor the creep of nitride fuel with technical purity is defined by the thermal component at mechanism of intergranular slip and by the radiation component, which plays a significant role at temperatures below 1100°C. Both types of creep in a first approximation have a linear dependence on the stress. (paper)

Availability note (English)

Available from http://dx.doi.org/10.1088/1757-899X/130/1/012030

Additional details

Publishing Information

Journal Title
IOP Conference Series. Materials Science and Engineering (Online)
Journal Volume
130
Journal Issue
1
Journal Page Range
[6 p.]
ISSN
1757-899X

Conference

Title
10. international school-conference on materials for extreme environment: Development, production and application
Acronym
MEEDPA10
Dates
19-23 Oct 2015
Place
Moscow (Russian Federation)

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
49094832
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
APPROXIMATIONS; CARBON; EQUATIONS; GRAIN SIZE; IMPURITIES; MIXED NITRIDE FUELS; NUCLEAR FUELS; OXYGEN; PLUTONIUM; POROSITY; STRESSES
Descriptors DEC
ACTINIDES; CALCULATION METHODS; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; MICROSTRUCTURE; NONMETALS; NUCLEAR FUELS; REACTOR MATERIALS; SIZE; SOLID FUELS; TRANSURANIUM ELEMENTS