Published November 1, 2018
| Version v1
Journal article
Influence of the plutonium content on thermochemical stability of a mixed nitride fuel
- 1. JSC «A.A. Bochvar High-technology Research Institute of Inorganic Materials», Moscow (Russian Federation)
- 2. National Research Nuclear University "MEPhI", Moscow (Russian Federation)
Description
The results of the thermogravimetric studies of mixed nitride uranium-plutonium (MNIT) fuel formulations at high temperatures (up to 2173 К) are presented. The rates of mass loss of mixed nitride are calculated as a function of the plutonium content. With the increase of the plutonium content in MNIT fuel the rate of mass loss increases. However, there is a deviation from this dependence for some compositions of MNIT fuel. (paper)
Availability note (English)
Available from http://dx.doi.org/10.1088/1742-6596/1133/1/012012Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Physics. Conference Series (Online)
- Journal Volume
- 1133
- Journal Issue
- 1
- Journal Page Range
- [7 p.]
- ISSN
- 1742-6596
Conference
- Title
- International Conference for Young Scientists, Specialists and Post-Graduates on Nuclear Reactor Physics
- Dates
- 3-7 Sep 2018
- Place
- Tverskaya Oblast (Russian Federation)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53034146
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- MASS TRANSFER; MIXED NITRIDE FUELS; NITRIDES; PLUTONIUM; THERMAL GRAVIMETRIC ANALYSIS; URANIUM
- Descriptors DEC
- ACTINIDES; CHEMICAL ANALYSIS; ELEMENTS; ENERGY SOURCES; FUELS; GRAVIMETRIC ANALYSIS; MATERIALS; METALS; NITROGEN COMPOUNDS; NUCLEAR FUELS; PNICTIDES; QUANTITATIVE CHEMICAL ANALYSIS; REACTOR MATERIALS; SOLID FUELS; THERMAL ANALYSIS; TRANSURANIUM ELEMENTS