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RISPost-Test Analyses of the CMMR-4 Test
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Understanding the final distribution of core materials and their characteristics is important for decommissioning the Fukushima Daiichi Nuclear Power Station (1F). Such characteristics depend on the accident progression ...
The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Creep strength enhanced ferritic (CSEF) steels including ASME Gr.91 are widely used in fossil power plants. In the advanced loop-type sodium-cooled fast reactor (SFR), modified 9Cr–1Mo steel (ASME Gr.91) is going to be ...
Strength of 316FR Joints Welded by Type 316FR/16 8 2 Filler Metals
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Type 316 stainless steel with lowcarbon and mediumnitrogen contents called 316FR stainless steel is a candidate structural material for reactor vessels and internals of futuregeneration fast breeder reactors (FBRs). The ...
Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The authors are developing an experimental technology for simulating severe accident (SA) conditions using simulant fuel material (ZrO2) that would contribute, not only to Fukushima Daiichi (1 F) decommissioning, but also ...