ODS Thin-wall Cladding Joining Technique Development

Program Document · Fri Oct 04 04:00:00 EDT 2019

OSTI ID:1604760

Gan, Jian ^[1]; Jerred, Nathan D ^[1]; Perez, Emmanuel Enrrique ^[1]; Mackowiak, Brady L ^[1]; Cordes, Nikolaus ^[1]; Bachhav, Mukesh ^[1]

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1. Idaho National Laboratory

ABSTRACT The oxide dispersion strengthened (ODS) materials are typically fabricated by powder mechanical alloying to form uniform distribution of high concentration nanometer size oxide particles for exceptional high temperature mechanical strength and enhanced radiation tolerance. This report summarizes the recent development on the weld techniques of joining the ODS cladding to the endplug as a part of accident tolerant fuels (ATF) program for both advanced light water reactor (LWR) and advanced fuel cycle (AFC) with fast reactor fuel cladding. It is crucial for the weld of ODS material to maintain the uniform distribution and fine size of oxide particles in the matrix. Pressure Resistance Weld (PRW) is a solid state joining technique without melting therefore a preferred joining technique for ODS materials. Samples joined with PRW were pressure burst tested. Detailed microstructural characterization in this work includes non-destructive 3D x-ray ?m-resolution computer-tomography (?-CT), optical microscopy, SEM/EBSD for grain-orientation-mapping, TEM, STEM/ASTAR for high resolution grain orientation and phase mapping, and APT for high-resolution 3D composition analysis.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: US DOE Office of Nuclear Energy
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1604760
• Report Number(s): INL/EXT-19-55825-Rev000
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ODS Thin-wall Cladding Joining
Technique Development