Study of thermal conductivity influence on MOX fuel behaviour
- 1. Institute for Nuclear Research, Pitesti (Romania)
Description
The present paper summarizes the influence of different thermal conductivity correlations on MOX fuel rod behaviour. In this respect, different MOX thermal conductivity correlations selected from various open literature sources were compared with each other as well as with conductivity correlations adopted in the TRANSURANUS code used in the present work for evaluation of MOX fuel rod performances. After comparing the different correlations, we introduced those from the open literature in the TRANSURANUS code. In order to confirm their effect on the fuel performance parameters we simulated an experiment from the International Fuel Performance Experiments (IFPE) database, IFA597 MOX, and we analysed the results obtained with the code using all the studied thermal conductivities versus the measurements on the fuel temperature, internal pressure and fission gas release. We noticed that some of the correlations underestimate significantly the measurements. Further, in our study we used only those correlations giving nearest values to the measurements. As a final conclusion, we can notify that standard TRANSURANUS and Halden correlations are the most indicated to be used for this type of analysis. (authors)
Additional details
Publishing Information
- Publisher
- Institute for Nuclear Research - Pitesti
- Imprint Place
- Pitesti (Romania)
- Imprint Title
- Proceedings of NUCLEAR 2017 international conference on sustainable development through nuclear research and education. Part 1/3
- Imprint Pagination
- 344 p.
- Journal Page Range
- p. 39-45
- ISSN
- 2066-2955
- Report number
- INIS-RO--0012
Conference
- Title
- 10. annual international conference on sustainable development through nuclear research and education
- Acronym
- NUCLEAR 2017
- Dates
- 24-26 May 2017
- Place
- Pitesti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 49086189
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADMINISTRATIVE PROCEDURES; COMPARATIVE EVALUATIONS; CORRELATIONS; COST; DATA; ECONOMICS; FISSION; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL RODS; MIXED OXIDE FUELS; PERFORMANCE; SIMULATION; SOCIO-ECONOMIC FACTORS; STANDARDS; THERMAL CONDUCTIVITY
- Descriptors DEC
- ENERGY SOURCES; EVALUATION; FUEL ELEMENTS; FUELS; INFORMATION; INSTITUTIONAL FACTORS; ISOTOPES; MATERIALS; NUCLEAR FUELS; NUCLEAR REACTIONS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 5 refs.