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Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels.

DE141154735

Publication Date	2014
Personal Author	McDeavitt, S. M.; Goldner, J.; Marschman, S.
Page Count	305
Abstract	This project had the following objectives: 1. Develop and customize in situ ion beam analysis tools to observe and characterize the nucleation and growth of gas bubbles in advanced U-TRU-Zr alloy fuel materials. 2. Quantify and model the fundamental phenomena relevant to fission gas induced swelling in advanced U-TRU-Zr alloy fuel materials. 3. Validate and benchmark the new multi-scale fuel swelling models using critical experiments performed using new in situ ion beam methods and post-test analysis. To achieve this objective, a comprehensive strategy is being implemented to provide insight and validation for the fundamental models that will enable multi-scale fuel performance predictions from first principles. The development experiments will focus on fission gas bubble nucleation and swelling in uranium-zirconium alloys containing transuranic (TRUs); however, the fundamental models developed for diffusion and fission gas mobility in the various phases present in U-TRU-Zr nuclear fuels will enable the modeling of other critical fuel performance phenomena in the future such as creep, component redistribution, and fuel-cladding mechanical or chemical interactions.
Keywords	Nuclear fuels Bubbles Alloys Fast reactors Fuel cycle Gases Isotopes Nucleation Performance codes Transuranium compounds
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77I - Reactor Fuels & Fuel Processing 77H - Reactor Engineering & Nuclear Power Plants
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	201503

Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels.

Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels.
DE141154735

Publication Date	2014
Personal Author	McDeavitt, S. M.; Goldner, J.; Marschman, S.
Page Count	305
Abstract	This project had the following objectives: 1. Develop and customize in situ ion beam analysis tools to observe and characterize the nucleation and growth of gas bubbles in advanced U-TRU-Zr alloy fuel materials. 2. Quantify and model the fundamental phenomena relevant to fission gas induced swelling in advanced U-TRU-Zr alloy fuel materials. 3. Validate and benchmark the new multi-scale fuel swelling models using critical experiments performed using new in situ ion beam methods and post-test analysis. To achieve this objective, a comprehensive strategy is being implemented to provide insight and validation for the fundamental models that will enable multi-scale fuel performance predictions from first principles. The development experiments will focus on fission gas bubble nucleation and swelling in uranium-zirconium alloys containing transuranic (TRUs); however, the fundamental models developed for diffusion and fission gas mobility in the various phases present in U-TRU-Zr nuclear fuels will enable the modeling of other critical fuel performance phenomena in the future such as creep, component redistribution, and fuel-cladding mechanical or chemical interactions.
Keywords	Nuclear fuels Bubbles Alloys Fast reactors Fuel cycle Gases Isotopes Nucleation Performance codes Transuranium compounds
Source Agency	Technical Information Center Oak Ridge Tennessee
NTIS Subject Category	77I - Reactor Fuels & Fuel Processing 77H - Reactor Engineering & Nuclear Power Plants
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	201503