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Accession Number
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DE2012-1042575
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Title
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Code Qualification of Structural Materials for AFCI Advanced Recycling Reactors.
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Publication Date
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May 2012
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Media Count
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211p
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Personal Author
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K. Natesan M. Li R. K. Nanstad S. Majumdar T. L. Sham
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Abstract
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This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Code Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR.
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Keywords
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Alloys
Creep
Economic analysis
Flexibility
Fracture poperties
Fuel cycle
Irradiation
Licensing
Neutrons
Physical properties
Power reactors
Reactor components
Recycling
Safety
Sodium
Stability
Stainless steels
Tensile properties
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Source Agency
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Technical Information Center Oak Ridge Tennessee
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NTIS Subject Category
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77H - Reactor Engineering & Nuclear Power Plants
71 - Materials Sciences
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Corporate Author
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Argonne National Lab., IL. Nuclear Engineering Div.
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Document Type
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Technical report
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Title Note
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N/A
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NTIS Issue Number
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1226
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Contract Number
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DE-AC02-06CH11357
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