NSUF 26-5647: Quantifying Hydrogen Defects in irradiated Zirconium Alloys

In this RTE, we propose leveraging the post-irradiation examination characterization capabilities at Brookhaven National Laboratory (NSLS-II) to quantify the state and amount of hydrogen trapped in the irradiation defects in zirconium alloys. Specifically, we propose employing X-ray Diffraction to systematically study a series of neutron irradiated, hydrogen containing neutron irradiated Zr alloy specimens located at Idaho National Laboratory. These experiments will provide insight into how hydrogen interacts with radiation-induced defects, which could lead to more accurate predictions of cladding embrittlement during reactor operation and better fuel performance codes. This knowledge is crucial for ensuring the long-term integrity of nuclear fuel cladding, particularly at service temperatures and to improve the safety and performance of nuclear reactors.

Additional Info

Field	Value
Awarded Institution	Stony Brook University
DOI	10.46936/NSUF/60017664
Embargo End Date	2028-04-22
Facility Tech Lead	Noé Morales, Simerjeet Gill
NSUF Call	FY 2026 RTE 1st Call
PI	David Sprouster
PIE Facilities	National Synchrotron Light Source II
Prep Facilities	Hot Fuel Examination Facility
Project Member	Dr. Peng Xu - Idaho National Laboratory (https://orcid.org/0000-0002-6899-4414)
Project Member	Professor David Sprouster, Assistant Professor - Stony Brook University (https://orcid.org/0000-0002-2689-0721)
Project Member	Dr. Aditya Shivprasad, Senior Technical Leader - Electric Power Research Institute (https://orcid.org/0000-0001-8515-2756)
Project Type	RTE