Code qualification of structural materials for AFCI advanced recycling reactors.
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 Boilermore »
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- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Argonne National Laboratory (ANL)
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- Country of Publication:
- United States
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; ALLOYS; CLINCH RIVER BREEDER REACTOR; CREEP; ECONOMICS; FLEXIBILITY; FRACTURE PROPERTIES; FUEL CYCLE; IRRADIATION; LICENSING; NEUTRONS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; RECYCLING; SAFETY MARGINS; SODIUM; STABILITY; STAINLESS STEELS; TENSILE PROPERTIES
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