Published April 1, 2016
| Version v1
Journal article
Structural-phase state and creep of mixed nitride fuel
Creators
- 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/130/1/012030Additional details
Identifiers
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