Paper 11 the Carburisation of Stainless Steels in Sodium Containing Carbon Impurities and Its Effect on Mechanical Properties

Thorley, A.W.; Tyzack, C.

doi:10.1680/eoeompins.44579.0015

Cited by 8 publications

(2 citation statements)

References 1 publication

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“…The carbides mass fractions determined by Rietveld analysis allowed the calculation of the carbon mass fraction trapped in carbides using Eq. 1: (1) with f x the mass fraction of the phase X and w X c the carbon mass fraction in the phase X.…”

Section: Phases Mass Fractionsmentioning

confidence: 99%

Determination of residual stress gradient in a Ti-stabilized austenitic stainless steel cladding candidate after carburization in liquid sodium at 500 °C and 600 °C

et al. 2021

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Section: Phases Mass Fractionsmentioning

confidence: 99%

Determination of residual stress gradient in a Ti-stabilized austenitic stainless steel cladding candidate after carburization in liquid sodium at 500 °C and 600 °C

et al. 2021

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“…Tensile data have been obtained from materials that were carburized in sodium to produce specific C-penetration depths. At temperatures between 400 and 800°C, the ultimate tensile elongation decreases with an increase in C concentration in the material (Kirschler et al 1969, Thorley et al 1970, Natesan et al 1972, Kirschler and Andrews 1968, Thorley and Tyzack 1971, Natesan et al 1975, Chopra and Natesan 1977, Natesan et al 1978. show the variation in the ultimate strength, uniform elongation, and total elongation for Types 304 and 316 SS after exposure to a sodium environment at temperatures between 425 and 700°C.…”

Section: Tensile Propertiesmentioning

confidence: 99%

Code qualification of structural materials for AFCI advanced recycling reactors.

Natesan¹,

Li²,

Nanstad³

et al. 2012

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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. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP) and the Power Reactor Innovative Small Module (PRISM), the NRC/Advisory Committee on Reactor Safeguards (ACRS) raised numerous safety-related issues regarding elevated-temperature structural integrity criteria. Most of these issues remained unresolved today. These critical licensing reviews provide a basis for the evaluation of underlying technical issues for future advanced sodium-cooled reactors.Major materials performance issues and high temperature design methodology issues pertinent to the ARR are addressed in the report. The report is organized as follows: the ARR reference design concepts proposed by the Argonne National Laboratory and four industrial consortia were reviewed first, followed by a summary of the major code qualification and licensing issues for the ARR structural materials. The available database is presented for the ASME Code-qualified structural alloys (e.g. 304, 316 stainless steels, 2.25Cr-1Mo, and mod.9Cr-1Mo), including physical properties, tensile properties, impact properties and fracture toughness, creep, fatigue, creep-fatigue in...

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Korrosion in Alkalimetallkreisläufen. I. Mechanismen und Phänomene

Borgstedt

1975

Materials & Corrosion

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Korrosion der Werkstoffe durch flüssige Alkalimetalle ist durch Lösen und Abscheiden von Material entlang eines Temperaturgefälles gekennzeichnet. Austauschreaktionen des Sauerstoffs und Kohlenstoffs, aber auch anderer nichtmetallischer oder metallischer Elemente spielen eine bedeutende Rolle. Vorgänge in technischen Anlagen mit umlaufenden Schmelzen von Li, Na oder K werden auf der Basis der Mechanismen gedeutet. Für den Einsatz oder die Kombination von Werkstoffen für solche Anlagen werden Empfehlungen gegeben. Die Korrosions‐ und Massetransportprobleme werden zu Fragen der Anlagensicherheit und verfügbarkeit in Beziehung gesetzt. Die Korrosionsprobleme werden durch Werkstoffauswahl, Auslegung von Komponenten und Spezifikation der Parameter der umlaufenden Alkalimetalle beherrscht.

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Paper 11 the Carburisation of Stainless Steels in Sodium Containing Carbon Impurities and Its Effect on Mechanical Properties

Cited by 8 publications

References 1 publication

Determination of residual stress gradient in a Ti-stabilized austenitic stainless steel cladding candidate after carburization in liquid sodium at 500 °C and 600 °C

Determination of residual stress gradient in a Ti-stabilized austenitic stainless steel cladding candidate after carburization in liquid sodium at 500 °C and 600 °C

Code qualification of structural materials for AFCI advanced recycling reactors.

Korrosion in Alkalimetallkreisläufen. I. Mechanismen und Phänomene

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