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Dissertations / Theses on the topic 'Ferritic-martensitic steel'

Author: Grafiati

Published: 4 June 2021

Last updated: 25 July 2025

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1

Foley, David Christopher. "Ferritic-martensitic steel subjected to equal channel angular extrusion." [College Station, Tex. : Texas A&M University, 2007. http://hdl.handle.net/1969.1/ETD-TAMU-2537.

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2

Benítez, Vélez Soraya. "Oxidation kinetics and mechanisms in HT-9 ferritic/martensitic stainless steel." [Gainesville, Fla.] : University of Florida, 2005. http://purl.fcla.edu/fcla/etd/UFE0012151.

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3

Ray, Lara L. "Friction stir welding of HT9 ferritic-martensitic steel: an assessment of microstructure and properties." Monterey, California: Naval Postgraduate School, 2013. http://hdl.handle.net/10945/34726.

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Approved for public release; distribution is unlimited<br>This thesis explores the processing-microstructure-property relationships in friction stir welded (FSW) HT9A ferritic-martensitic steel. HT9 has previously been studied as a structural component for fusion/fission based reactors; however, the changes in material microstructure and properties after friction stir welding have not been considered. HT9A steel plate was friction stir welded with a series of increasing heat inputs. The microstructure of this welded material was characterized using optical and electron microscopy. The mechanic

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4

Zhang, Kuo [Verfasser]. "Characterization and Modeling of the Ratcheting Behavior of the Ferritic-Martensitic Steel P91 / Kuo Zhang." Karlsruhe : KIT Scientific Publishing, 2017. http://www.ksp.kit.edu.

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5

Marino, Daniel. "Using nonlinear ultrasound measurements to assess the stage of thermal damage in modified 9%Cr ferritic martensitic steel." Thesis, Georgia Institute of Technology, 2014. http://hdl.handle.net/1853/53027.

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This research investigates second harmonic generation in Rayleigh surface waves propagating in 9%Cr ferritic martensitic steel. Previous experimental results show that the nonlinearity parameter is sensitive to certain changes in a material's properties such as thermal embrittlement and hardness changes. Therefore, the nonlinearity parameter can be used as an indicator of thermal damage due to changes in dislocation density and precipitations. The specimens are isothermally aged for different holding times to create progressive changes in the microstructure and obtain different levels of therm

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6

Zhang, Kuo [Verfasser], and J. [Akademischer Betreuer] Aktaa. "Characterization and Modeling of the Ratcheting Behavior of the Ferritic-Martensitic Steel P91 / Kuo Zhang. Betreuer: Dr. J. Aktaa." Karlsruhe : KIT-Bibliothek, 2015. http://d-nb.info/1093559241/34.

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7

Patra, Anirban. "Modeling the mechanical behavior and deformed microstructure of irradiated BCC materials using continuum crystal plasticity." Diss., Georgia Institute of Technology, 2013. http://hdl.handle.net/1853/50366.

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The mechanical behavior of structural materials used in nuclear applications is significantly degraded as a result of irradiation, typically characterized by an increase in yield stress, localization of inelastic deformation along narrow dislocation channels, and considerably reduced strains to failure. Further, creep rates are accelerated under irradiation. These changes in mechanical properties can be traced back to the irradiated microstructure which shows the formation of a large number of material defects, e.g., point defect clusters, dislocation loops, and complex dislocation networks. I

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8

Smith, Andrew Logan Mr. "Thermodynamic Evaluation and Modeling of Grade 91 Alloy and its Secondary Phases through CALPHAD Approach." FIU Digital Commons, 2018. https://digitalcommons.fiu.edu/etd/3773.

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Grade 91 (Gr.91) is a common structural material used in boiler applications and is favored due to its high temperature creep strength and oxidation resistance. Under cyclic stresses, the material will experience creep deformation eventually causing the propagation of type IV cracks within its heat-affected-zone (HAZ) which can be a major problem under short-term and long-term applications. In this study, we aim to improve this premature failure by performing a computational thermodynamic study through the Calculation of Phase Diagram (CALPHAD) approach. Under this approach, we have provided a

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9

Sierra, Robinson. "Investigation of the mechanical behaviour of TRIP steels using FEM." Thesis, McGill University, 2006. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=99793.

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The need to develop light-weight and high strength materials for car frames which improve fuel efficiency and provide increased passenger safety during dynamic events such as automobile crashes has been the focus of the steel and automobile industries for the past 30 years. In recent years, the development of high strength steels such as multi-phase TRIP (Transformation-Induced Plasticity)-aided steels have shown great promise due to their excellent combination of high strength and ductility. The savings in automobile weight is provided by the inherent strength of TRIP steels which allows for

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10

Morgan, Terence S. "Microstructural effects of neutron irradiation on ferritic/martensitic stainless steels." Thesis, Loughborough University, 1992. https://dspace.lboro.ac.uk/2134/13768.

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A commercial grade 12%CrMo VNb ferritic/martensitic stainless steel in the form of parent plate and high-nickel off-normal weld material has been fast neutron irradiated to equivalent damage levels of 33 and 50 dpa at 400 and 465°C respectively. The microstructural and microchemical changes induced in the irradiated material, together with as-tempered and thermal control material, have been determined to high resolution by conventional transmission electron microscopy and the use of a field emission gun scanning transmission electron microscope (FEGSTEM). Equilibrium (co )segregation of chromi

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11

McGinnis, Alexander L. "Diffusion Couple Alloying of Refractory Metals in Austenitic and Ferritic/Martensitic Steels." Thesis, Monterey, California. Naval Postgraduate School, 2012. http://hdl.handle.net/10945/6832.

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This thesis utilized the diffusion couple approach to evaluate the addition of molybdenum, niobium, tantalum, and tungsten to 316 stainless (316SS) and alloy HT9 steels. Refractory elements have been previously studied as alloying candidates to mitigate problems such as radiation-induced segregation, void swelling, and irradiation creep in reactor steels. Diffusion couples were characterized via energy dispersive x-ray spectroscopy (EDS) and nanoindentation to examine refractory element solubility, diffusivity, and the effects these elements have on hardness and elastic modulus in 316SS and al

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12

Adetunji, Gbadegesin James. "Microstructural control and high-temperature mechanical property of ferritic/martensitic steels for nuclear reactor application." Thesis, Loughborough University, 1988. https://dspace.lboro.ac.uk/2134/32904.

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The materials under study are 9–12% Cr ferritic/martensitic steels, alternative candidate materials for application in core components of nuclear power reactors. This work involves: (1) investigation of high temperature fracture mechanism during slow tensile and limited creep testing at 600°C; (2) extensive study of solute element segregation, theoretically using proposed model of combined equilibrium and non-equilibrium mechanisms; and experimentally using field emission gun scanning transmission electron microscopy; (3) investigation of effects by thermal ageing and irradiation on microstruc

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13

Huang, Shaosong. "INITIAL STAGE OF DEFECT STRUCTURAL EVOLUTION IN F82H AND ITS MODEL ALLOYS BY IRRADIATION DAMAGE." 京都大学 (Kyoto University), 2014. http://hdl.handle.net/2433/188579.

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14

Bredda, Eduardo Henrique. "Caracterização microestrutural do aço ODS Eurofer recozido isotermicamente até 1350oC." Universidade de São Paulo, 2015. http://www.teses.usp.br/teses/disponiveis/97/97134/tde-14092016-180913/.

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O aço ferrítico-martensítico ODS Eurofer com 9%pCr (ODS - do inglês oxide dispersion strengthened), objeto de estudo dessa dissertação, é um potencial candidato para fins estruturais em reatores de fusão nuclear. Este material foi produzido via metalurgia do pó e consolidado por prensagem isostática. Em seguida sofreu laminação cruzada a quente e revenimento em 750°C por 2h. Esta foi a condição como recebida desse aço, o qual foi cedido pelo KIT (Karlsruher Institut für Technologie - Alemanha). Este aço possui 0,3%p de partículas de ítria (Y2O3) com diâmetro entre 10 e 30 nm. Uma das finalidad

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15

Šohaj, Pavel. "Strukturní stabilita žárupevných ocelí a jejich svarů." Master's thesis, Vysoké učení technické v Brně. Fakulta strojního inženýrství, 2009. http://www.nusl.cz/ntk/nusl-228381.

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The structural stability of creep-resistant steels P22, P91 and Eurofer´97 and structural stability of weld joint P22/P91 have been studied. The microstructural changes during annealing at temperatures of 500 – 900°C were examined. The state of equilibrium have been simulated using the ThermoCalc software. The computed results were compared with published data. A good agreement between the simulation and the published data was observed.

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16

Bouhieda, Soraya. "Etude des premiers instants d'oxydation d'un acier ferrito-martensitique FE-12CR dans le CO2." Phd thesis, Ecole Nationale Supérieure des Mines de Saint-Etienne, 2012. http://tel.archives-ouvertes.fr/tel-00848596.

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Dans le cadre du développement des réacteurs nucléaires de 4ème génération et plus particulièrement du réacteur à neutrons rapides refroidi au sodium (SFR), le CO2 supercritique, dans un cycle de Brayton, a été identifié comme fluide potentiel en remplacement de la vapeur d'eau dans le cycle de conversion de l'énergie. Les aciers ferrito-martensitiques contenant 9 à 12 % en poids de Cr sont de bons candidats pour la réalisation d'échangeurs thermiques car ils présentent de bonnes propriétés mécaniques jusqu'à une température de 600°C, une forte conductivité thermique, un faible coefficient d'e

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17

Whitt, Harrison Collin. "Creep and Creep-fatigue Deformation Studies in 22V and P91 Creep-strength EnhancedFerritic Steels." The Ohio State University, 2019. http://rave.ohiolink.edu/etdc/view?acc_num=osu1555603135480185.

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18

Bischoff, Jeremy. "Evolution of the oxide structure of ferritic-martensitic steels exposed to supercritical water." 2008. http://etda.libraries.psu.edu/theses/approved/WorldWideIndex/ETD-2716/index.html.

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