Investigation of fuel-cladding chemical interaction (FCCI) in irradiated U-Pu-Zr fuel

Principal Investigator
Name:
Assel Aitkaliyeva
Email:
[email protected]
Phone:
(208) 526-6918
Team Members:
Name: Institution: Expertise: Status:
Luca Capriotti Idaho National Laboratory PIE, metallic fuel, oxide fuels, fuel behavior irradiation Other
Jason Harp Idaho National Laboratory electron microscopy, nuclear fuel fabrication, PIE, tomography, TRISO, uranium compounds, fabrication, mixed oxides, gamma spectrometry Other
Casey McKinney University of Florida data analysis Graduate Student
Experiment Details:
Experiment Title:
Investigation of fuel-cladding chemical interaction (FCCI) in irradiated U-Pu-Zr fuel)
Work Description:
The proposed project will examine U-20Pu-10Zr fuel specimens irradiated in Advanced Test Reactor (ATR) as part of the Advanced Fuels Campaign's (AFC-2E) series of experiments. Key performance parameters were irradiation growth and swelling, He and fission gas release fractions, fission product and fuel constituent migration, and fuel cladding chemical interaction (FCCI). Each AFC experiment consists of a fuel material (actinide alloy or compound) encapsulated in a sealed cladding material (HT-9 ferritic martensitic steel) and further encapsulated in a stainless steel capsule that serves as the primary boundary between the ATR primary coolant and the experiment. Multiple rodlets with varying compositions were irradiated and subjected to a standard set of postirradiation (PIE) measurements in Hot Fuels Examination facility (HFEF) at INL. PIs will conduct advanced PIE to obtain microscopic elemental and structural information in the fuel, in the cladding, and in the FCCI region.
Project Summary
Fast reactor technology provides a path to transmute long-lived transuranic actinide isotopes contained in spent nuclear fuels. In an effort to aid to the development of these fuels, we propose to examine a sample from the Advanced Fuels Campaign (AFC) AFC-2E experiment, which contains a historical casting from the Integral Fast Reactor (IFR) Program to provide comparison between the performance of archived and newly cast ternary fuels.

The objective of the proposed research is to conduct detailed microstructural examination of the phases formed within fuel-cladding chemical interaction (FCCI) region of irradiated U-20Pu-10Zr fuel. The PIs will conduct scanning and transmission electron microscopy and X-ray spectroscopy to obtain microscopic elemental and structural information in the fuel, in the cladding, and in the FCCI region. This proposal will fill the knowledge gap on FCCI in irradiated U-Pu-Zr fuels, thus directly benefiting Fuel Cycle Research and Development (FCRD) at DOE-NE.
Relevance
Technical relevance of the proposal is directly related to the Department of Energy Office of Nuclear Energies mission to advance nuclear power as a resource capable of meeting the nation?s energy, environmental, and national security needs, and the mission to develop next-generation advanced nuclear fuels. The proposed project will benefit The Fuel Cycle Research and Development (FCRD) project, funded by DOE NE and Advanced Fuel Cycle Initiative (AFCI). Fast reactor technology provides a path to transmute long-lived transuranic actinide isotopes contained in spent nuclear fuels. However, development and demonstration of this technology requires an in-depth understanding of the fuel performance. As such, candidate nuclear fuels and possible transmutation compositions undergo irradiation testing in a prototypic fast reactor spectrum. Postirradiation examination of these materials provides data on reactor fuel performance and input into future fuel design choices. In an effort to aid to the development of these fuels, we propose to examine a sample from the AFC-2E experiment, which contains a historical casting from the Integral Fast Reactor (IFR) Program to provide comparison between the performance of archived and newly cast ternary fuels.
Conference Publications

"Chemical and microstructural analysis of irradiated mixed oxide fuels" Assel Aitkaliyeva, Riley Parrish, Jason Harp, The Minerals, Metals and Materials Society (TMS) Annual Meeting & Exhibition March 11-15, (2018)

"TEM Analysis of Irradiated Mixed-oxide Fuel" Assel Aitkaliyeva, Riley Parrish, Jason Harp, American Nuclear Society Student Conference 2018 April 5-7, (2018)

"Microscopy and microanalysis of nuclear fuels" Assel Aitkaliyeva, Materials Research Society (MRS) Spring Meeting & Exhibit April 2-6, (2018)