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Tuesday, April 28, 2020 | History

3 edition of Long-term embrittlement of cast duplex stainless steels in LWR systems found in the catalog.

Long-term embrittlement of cast duplex stainless steels in LWR systems

Long-term embrittlement of cast duplex stainless steels in LWR systems

semiannual report, April-September 1987

by

  • 400 Want to read
  • 34 Currently reading

Published by Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, D.C .
Written in English

    Subjects:
  • Steel, Stainless -- Embrittlement.

  • Edition Notes

    Other titlesLong term embrittlement of cast duplex stainless steels in LWR systems.
    Statementprepared by O.K. Chopra, H.M. Chung.
    ContributionsChung, H. M., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.
    The Physical Object
    FormatMicroform
    Pagination1 v.
    ID Numbers
    Open LibraryOL15375804M

    This modifies the precipitation behaviour and the resulting change in mechanical properties in duplex stainless steels when embrittled at C as compared to binary iron chromium systems. The precipitation behaviour of duplex stainless steel at C and the effect on tensile, fracture and fatigue behaviour are reviewed in this article. Technical Acronyms A B C D E F G H I J K L M N O P Q R S T U V W X Y Z A 1 2 a - Annum 3 A - Area 4 AA - Ash Analysis 5 AA - Advanced Analysis 6 A/A - Air to Air 7. Steels containing in excess of 11% Cr, will display stainless (rust-resistant) qualities when exposed to the atmosphere; thus, this group or, more properly, family of alloys is termed ‘‘stainless steels.’’ In this chapter, the ferritic and martensitic stainless steels will also be discussed. Password requirements: 6 to 30 characters long; ASCII characters only (characters found on a standard US keyboard); must contain at least 4 different symbols;.


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Long-term embrittlement of cast duplex stainless steels in LWR systems Download PDF EPUB FB2

@article{osti_, title = {Long-term embrittlement of cast duplex stainless steels in LWR systems. Semiannual report, October March Volume 7, No.1}, author = {Chopra, O.

K.}, abstractNote = {This progress report summarizes work performed by Argonne National Laboratory on long-term thermal embrittlement of cast duplex stainless steels in LWR systems during the six months from.

@article{osti_, title = {Long-term embrittlement of cast duplex stainless steels in LWR systems. Semiannual report, April--September Volume 7, No. 2}, author = {Chopra, O K}, abstractNote = {This progress report summarizes work performed by Argonne National Laboratory on longterm thermal embrittlement of cast duplex stainless steels in LWR systems during the six months from April.

Get this from a library. Long-term embrittlement of cast duplex stainless steels in LWR systems: semiannual report, October March [O K Chopra; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering.; Argonne National Laboratory.]. Get this from a library.

Long-term embrittlement of cast duplex stainless steels in LWR systems: semiannual report, April-September [O K Chopra; H M Chung; U.S. Nuclear Regulatory Commission.

Office of Nuclear Regulatory Research. Division of Engineering.]. Cast austenitic stainless steel (CASS) materials are used extensively in reactor coolant pressure boundary systems as well as core support structure and reactor internals.

However, these materials have a duplex structure consisting of austenite and ferrite phases and are susceptible to thermal aging embrittlement during reactor service. Cast stainless steels used in valve bodies, pump casings, piping, and other components in coolant systems of light water reactors (LWRs) suffer a loss in fracture toughness due to ther- mal aging after many years of service at temperatures in the range of –°C (≈–°F).File Size: 1MB.

Duplex stainless steels have been adopted by many industries to varying degrees. They are the workhorse corrosion resistant alloy (CRA) of the oil and gas industry, and are also widely used in the chemical and process industries for their SCC and corrosion resistance Category: Long Term Embrittlement Of Cast Duplex Stainless Steels In Lwr Systems.

The long term aging behaviour of a large number of Mo bearing and Mo free heats of cast duplex stainless steels has been studied between and °C in terms of hardness and impact Charpy.

Long-term embrittlement of cast duplex stainless steels in LWR systems O. Chopra Stainless, Stainless steel, Congresses, Corrosion Ludlum Steel Corporation, 2 books Genshiryoku Anzen Kiban Kikō, 2 books J. Dunning, 2 books D. Alexander, 1 book A. Parshin, 1 book.

Lists. This modifies the precipitation behaviour and the resulting change in mechanical properties in duplex stainless steels when embrittled at °C as compared to binary iron chromium systems.

The precipitation behaviour of duplex stainless steel at °C and the effect on tensile, fracture and fatigue behaviour are reviewed in this by: Thermal aging embrittlement in duplex stainless steels There has been a concern that the cast duplex stainless steel components in LWR systems can be susceptible to the thermal aging-induced embrittlement at reactor operating temperatures ranging from to °C [].

The thermal aging of cast stainless steels can cause an increase. Methodology for Estimating Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels During Service in Light Water Reactors Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems: Semiannual Report Oct.

–March Vol. 6, No. 1, ANL/ Chopra, O. K.,“ Long-Term Embrittlement of Cast Cited by: 6. Chopra and H. Chung, Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems: Semiannual Reports, Argonne National Laboratory, (A) ANL, October September(B) ANL, October March(C) ANL, April-September Google ScholarCited by: 1.

Abstract. Cast austenitic stainless steels (CASS) consist of a dual-phase microstructure of delta ferrite and austenite. The ferrite phase is critical for the service performance of CASS alloys, but can also undergo significant microstructural changes at elevated temperatures, leading Author: Y.

Chen, C. Xu, X. Zhang, W.-Y. Chen, J.-S. Park, J. Almer, M. Li, Z. Li, Y. Yang, A. Rao, B. Ale. This progress report summarizes work performed by Argonne National Laboratory on long-term embrittlement of cast duplex stainless steels in LWR systems during the six months from April to.

Prediction Method of Tensile Properties and Fracture Toughness of Thermally Aged Cast Duplex Stainless Steel Piping ASME Paper No. PVP /PVP Assessment of thermal embrittlement in duplex stainless steels and for nuclear power applications J.D.

Tucker,a,⇑ M.K. Millerb and G.A. Youngc aOregon State University, Rogers Hall, Corvallis, ORUSA bOak Ridge National Laboratory, PO BoxOak Ridge, TNUSA cKnolls Atomic Power Laboratory, PO BoxNiskayuna, NYUSA. Duplex stainless steels (DSS) are prone to phase transformations when exposed to temperatures in excess of °C [1].

Microstructure changes are typically accompanied by embrittlement and the loss of corrosion resistance, affecting the endurance and performance of. Cr concentration as high as 60–65% have been measured in α′-phase in cast duplex stainless steel after aging to o h at °C.

Cr, as a primary constituent of stainless steels, has been known to be the most important element which influences the corrosion properties of stainless steels. The variation in Cr concentration also Cited by: Hydrogen embrittlement (HE) also known as hydrogen assisted cracking (HAC) and hydrogen-induced cracking (HIC), describes the embrittling of metal after being exposed to is a complex process that is not completely understood because of the variety and complexity of.

A range of 22%Cr duplex and 25%Cr superduplex stainless steels including parent pipe, plate, forgings and bars, welds (cross-weld and all weld metal specimens) and simulated heat affected zones (HAZs), Table 1 and Fig.1, were selected for constant load tensile testing under cathodic protection, to examine HESC behaviour.

Simulated HAZs were. The effect of °C embrittlement on microstructure development of grade duplex stainless steel was investigated.

Spinodal decomposition products and associated precipitates in ferrite, austenite, and at interphase boundaries were characterized using analytical transmission electron microscopy (TEM) and scanning electron microscopy (SEM) by: 2.

Tensile properties of duplex UNS s and lean duplex UNS S steels and the influence of short duration ºC aging. Sérgio Souto Maior Tavares I, *; Juan Manuel Pardal I; Hamilton Ferreira Gomes de Abreu II; Cristiana dos Santos Nunes II; Manoel Ribeiro da Silva III.

I Escola de Engenharia, Universidade Federal Fluminense - UFF, Rua Passo da Pátria,CEPNiterói, RJ. Sigma Phase Characterization in AISI Stainless Steel - Volume 11 Issue S02 - X Tang Skip to main content Accessibility help We use cookies to distinguish you from other users and to provide you with a better experience on our by: The work reported in this paper correlates microstructure development after low temperature embrittlement heat treatments with pitting corrosion susceptibility in grade duplex stainless steel.

Heat-treatments at °C for up to hours were carried out and microstructures characterised using scanning electron microscopy (SEM) and micro Cited by: 4. Change of microstructure and fracture behavior induced by long term aging of type stainless steels Miyahara, K.

/ Bae, D. / Kimura, T. / Shimoide, Y. / Italian Group on Fracture | print version. A Critical Review of Weld Metal Embrittlement these steels. Much progress has been made in the understanding of these factors, but the information is consid­ toughness of stress relieving and long-term service in the temperature range of ° F are discussed.

Table 1 Joining PlateFile Size: 2MB. MPC °C Embrittlement of Duplex Stainless Steel—A Comprehensive Microstructure Characterization Study - 26 May MPC Anisotropy in Residual Stress Measurements in Aluminum Alloys Used in the Aerospace Industry - 26 May However, the sigmatized / H (UNS S / UNS S) stainless steel weld metal behaved brittle in both Charpy and Omega tests.

INTRODUCTION Sigma phase embrittlement is a well-recognized material degradation mechanism affecting austenitic stainless steels in fluidized catalytic cracking units (FCCU) in the oil refinery : Jorge L. Hau. L welding duplex stainless steel has been irradiated at °C with 2 MeV protons, corresponding to a dose of 3 dpa at the maximum depth of 20 μm.

Microhardness of the δ-ferrite and austenite phases was studied before and after proton irradiation using in situ nanomechanical test system (ISNTS).

The locations of the phases for indentations placement were obtained by scanning probe Cited by: 1. long term and improve the spread of protection. Experience gained over the past 20 years has led to the development of a CP design philosophy for offshore structures and pipelines, which identifies three different current density requirements as needing to be satisfied: o High Initial Current Density-to rapidly generate highly alkaline.

discussed, in absence of available data. The focus will be on T91 steels and L stainless steels in contact with LBE or lead. This chapter is organised as follows: Section focuses on liquid metal embrittlement (LME). It is subdivided into two parts.

Section is dedicated to wetting, which is one of the two main requirements for. We found that welding rod of the same trademark but different batch has distinct different tendency of brittleness when they are experienced step cooling embrittling treatment process.A series of Cr-1MoV steel welds were prepared using the manual arc.

The notch toughness properties were assessed in the PWHT condition and after a temper embrittlement step-cooling treatment. the J and X Cited by: 1. Intermetallic Phase Precipitation in Duplex Stainless Steels and Weld Metals: Metallurgy, Influence on Properties, Welding and Testing Aspects: $ Add to Cart: WRC T.

Adams: Assessment, Sample Problems and Commentary on Design for Section III, Division 3 (NUPACK) of the ASME Boiler and Pressure Vessel Code: $ Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors Jeremy T.

Busby, Gabriel Ilevbare, Peter L. Andresen (eds.) Year: You can write a book review and share your experiences. Other readers will always be interested in your opinion of the books you've read.

20th International Conference on STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY Dipoli Congress Centre, Espoo (Helsinki), Finland August 9–14, SMiRT 20 – Book of abstracts Vol.

1 ISBN (soft back ed.) ISSN –(soft back ed.). Industrial processing of duplex stainless steels usually includes two annealing steps: one intermediate after the hot rolling, and the final one after the cold rolling. The aim of this work is to evaluate the effect of final annealing temperature on pitting corrosion behavior of a lean alloy.

Contents Metals mining and processing. Behaviour and characterisation. Steel. Design, manufacture and applications. High temperature materials and power generation. Duplex Stainless Steels Duplex stainless steels have lower amounts of nickel than the austenitic grades, with the result that some of the austenite transforms to ferrite.

Generally, the alloying element and heat treatments are controlled to form equal amounts of ferrite and austenite. The principal advantages over the fully austenitic grades.

The Limiting Section Thickness for Duplex Stainless Steels Roger Francis (RFMaterials) a.m. a.m. C Experience with Standard Duplex Stainless Steel Seawater Pump Sivuyile Funani (Saudi Basic Industries in Arabian Gulf Seawater Conditions Corporation) a.m. Cast austenitic stainless steels (CASS)Cast Austenitic Stainless Steels (CASS) consist of a dual-phase microstructure of delta ferrite and austenite.

The ferrite phase is critical for the service performance of CASS alloys, but can also undergo significant microstructural changes at elevated temperatures, leading to severe embrittlement.Corrosion of stainless steels AISI and AISI induced by sulfate reducing bacteria in anoxic groundwater Authors: Rajala, Pauliina; Bomberg, Malin; Huttunen-Saarivirta, Elina; Carpén, Leena CorrosionConference and Expo, 26 - 30 MarchNew Orleans, LA USA Corrosion Conference and Expovol.

5. Thermal Aging Phenomena in Cast Duplex Stainless Steels. SciTech Connect. Byun, T. S.; Yang, Y.; Overman, N. R. Cast stainless steels (CASSs) have been extensively used for the large components of light water reactor (LWR) power plants such as primary coolant piping and pump casing.

The thermal embrittlement of CASS components is one of the.