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Overview of a Welding Development Program for a Ni-Cr-Mo-Gd Alloy.

DE2008912909

Publication Date	2007
Personal Author	Hurt, W. L.; Mizia, R. E.; Clark, D. E.
Page Count	4
Abstract	The National Spent Nuclear Fuel Program (NSNFP), located at the Idaho National Laboratory, coordinates and integrates management and disposal of U.S. Department of Energy-owned spent nuclear fuel. These management functions include using the DOE standardized canister for packaging, storage, treatment, transport, and long-term disposal in the Yucca Mountain Repository. Nuclear criticality must be prevented in the postulated event where a waste package is breached and water (neutron moderator) is introduced into the waste package. Criticality control will be implemented by using a new, weldable, corrosion-resistant, neutron-absorbing material to fabricate the welded structural inserts (fuel baskets) that will be placed in the standardized canister. The new alloy is based on the Ni-Cr-Mo alloy system with a gadolinium addition. Gadolinium was chosen as the neutron absorption alloying element because of its high thermal neutron absorption cross section. This paper describes a weld development program to qualify this new material for American Society of Mechanical Engineers (ASME) welding procedures, develop data to extend the present ASME Code Case (unwelded) for welded construction, and understand the weldability and microstructural factors inherent to this alloy.
Keywords	Alloys Welding Containers Spent fuels Neutron absorbers Absorption Crticality Cross sections Gadolinium Nickel alloys Packaging Radioactive waste storage Radioactive waste treatment Waste disposal Criticality Thermal neutrons Yucca Mountain
Source Agency	Technical Information Center Oak Ridge Tennessee
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	200814
Contract Number	DE-AC07-99ID-13727

Overview of a Welding Development Program for a Ni-Cr-Mo-Gd Alloy.

Overview of a Welding Development Program for a Ni-Cr-Mo-Gd Alloy.
DE2008912909

Publication Date	2007
Personal Author	Hurt, W. L.; Mizia, R. E.; Clark, D. E.
Page Count	4
Abstract	The National Spent Nuclear Fuel Program (NSNFP), located at the Idaho National Laboratory, coordinates and integrates management and disposal of U.S. Department of Energy-owned spent nuclear fuel. These management functions include using the DOE standardized canister for packaging, storage, treatment, transport, and long-term disposal in the Yucca Mountain Repository. Nuclear criticality must be prevented in the postulated event where a waste package is breached and water (neutron moderator) is introduced into the waste package. Criticality control will be implemented by using a new, weldable, corrosion-resistant, neutron-absorbing material to fabricate the welded structural inserts (fuel baskets) that will be placed in the standardized canister. The new alloy is based on the Ni-Cr-Mo alloy system with a gadolinium addition. Gadolinium was chosen as the neutron absorption alloying element because of its high thermal neutron absorption cross section. This paper describes a weld development program to qualify this new material for American Society of Mechanical Engineers (ASME) welding procedures, develop data to extend the present ASME Code Case (unwelded) for welded construction, and understand the weldability and microstructural factors inherent to this alloy.
Keywords	Alloys Welding Containers Spent fuels Neutron absorbers Absorption Crticality Cross sections Gadolinium Nickel alloys Packaging Radioactive waste storage Radioactive waste treatment Waste disposal Criticality Thermal neutrons Yucca Mountain
Source Agency	Technical Information Center Oak Ridge Tennessee
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	200814
Contract Number	DE-AC07-99ID-13727