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RISComparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Development of liquid lead cooled nuclear systems requires consideration of compatibility issues with the construction materials. In order to understand the corrosion or passivation behavior of the 316 L austenitic stainless ...
On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The fretting phenomenon was responsible for over 50% of fuel failure cases in the years 2010–2015 according to International Atomic Energy Agency (IAEA). It shows the scale of the problem for the nuclear power generation ...
Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Zirconium-based alloys are one of the most significant materials in thermal-neutron reactor systems. With very low neutron capture cross section, good corrosion resistance, mechanical strength and resistance to neutron ...
The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The presented article outlines and describes the processes involved in the creation and testing of the passivation layer that was created during hot functional tests (HFTs) at the third unit of the nuclear power plant (NPP) ...
From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
Publisher: American Society of Mechanical Engineers (ASME)
Abstract: Nuclear grade fuel claddings act as a barrier against release of fuel particles into the coolant water during nuclear power plant operation, handling, and wet or dry storage of the spent fuel rods. The integrity of claddings ...