Published December 2018
| Version v1
Book
New Catalog on (U,Pu)O2 Properties for Fast Reactors and First Measurements on Irradiated and Non-irradiated Fuels Within the ESNII+ Project
Description
The thermal conductivity is an important parameter for the assessment of the FBR fuel thermal behavior during irradiation. In this study, the effect of burn-up on the thermal conductivity of FBR MOX fuel is investigated experimentally. The thermal diffusivity of FBR fuel with a burn-up of 13 at.% was measured by the laser flash technique and the thermal conductivity was deduced. It is shown that the thermal conductivity is higher than could be predicted with correlations issued from LWR UO2 and MOX results. This effect is interpreted as being due to the diffusion of fission products out of the fuel matrix, leading to the formation of the JOG. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 9 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006340
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CATALOGS; DIFFUSION; FBR TYPE REACTORS; FISSION PRODUCTS; IRRADIATION; MIXED OXIDE FUELS; PLUTONIUM DIOXIDE; SPENT FUELS; THERMAL CONDUCTIVITY; THERMAL DIFFUSIVITY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; DOCUMENT TYPES; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMODYNAMIC PROPERTIES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 10 refs., 8 figs.
- Secondary number(s)
- IAEA-CN--245-525