Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors

Rowcliffe, A.F.; Mansur, L.K.; Hoelzer, David T.; Nanstad, R.K.

doi:10.1016/j.jnucmat.2009.03.023

Cited by 167 publications

(84 citation statements)

References 50 publications

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“…[40][41][42]). The effects discussed in this paper concentrate mainly on topics which directly affect safety and life-time of components of advanced nuclear plants [43,44]. Table 3 lists the following types of irradiation damage: displacement damage (formation of point defect clusters and loops), irradiation induced phase transformations and production of helium as a result of nuclear reactions.…”

Section: Irradiation Damagementioning

confidence: 99%

Damage assessment in structural metallic materials for advanced nuclear plants

Hoffelner

2010

J Mater Sci

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Future advanced nuclear plants are considered to operate as cogeneration plants for electricity and heat. Metals and alloys will be the main portion of structural materials employed (including fuel claddings). Due to the operating conditions these materials are exposed to damaging conditions like creep, fatigue, irradiation and its combinations. The paper uses the most important alloys: ferritic-martensitic steels, superalloys, oxide dispersion strengthened steels and to some extent titanium aluminides to discuss its responses to these exposure conditions. Extrapolation of stress rupture data, creep strain, swelling, irradiation creep and creep-fatigue interactions are considered. Although the stress rupture-and the creep behavior seem to meet expectations, the long design lives of 60 years are really challenging for extrapolations and particularly questions like negligible creep or occurrence of diffusion creep need special attention. Ferritic matrices (including oxide dispersion strengthened (ODS), steels) have better irradiation swelling behavior than austenites. Presence and size of dispersoids having a strong influence on high-temperature strength bring only insignificant improvements in irradiation creep. A strain-range-separation based approach for creep-fatigue interactions is presented which allows a real prediction of creep-fatigue lives. An assessment of capabilities and limitations of advanced materials modeling tools with respect to damage development is given.

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Section: Irradiation Damagementioning

confidence: 99%

Damage assessment in structural metallic materials for advanced nuclear plants

Hoffelner

2010

J Mater Sci

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“…Several neutron irradiation studies were carried out on commercial Ni-base alloys, including Alloys 600, 625, 702, 718, 800, 706, PE16, Hastelloy X, and Rene 41, in the 1958-1974 time frame. 58 Proton irradiations were completed to investigate effects of irradiation on the microstructure of Inconel 600 alloy. 59,60 In addition, tensile properties of Inconel 718 have been investigated after neutron irradiation to 0.0006-1.2 dpa at 60-100°C in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL), as well as SA 316LN stainless steel are also included for comparison.…”

Section: Inconelmentioning

confidence: 99%

In-situ Creep Testing Capability Development for Advanced Test Reactor

Kim¹,

Rempe²,

Knudson³

et al. 2010

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“…Como resultado, aumento da força e estabilidade química são mantidas em temperaturas acima de 540°C [1,2,5]. Há um vasto campo de aplicações para superligas, especialmente como componentes críticos para as indústrias do espaço aéreo, petroquímicas e de geração de energia, como Estudantelâminas de turbina e discos, válvulas, molas ou parafusos para reatores nucleares ou vasos de tubulação e de reação para plantas petroquímicas [2].Em particular, a superliga de Ni 718 apresenta um excelente conjunto de propriedades, como alta resistência e tenacidade em temperaturas criogênicas até 650°C, e resistência a ambientes agressivos como água marinha, motor de ônibus espacial ou o núcleo de reatores nucleares de PWR [6][7][8] , além de poder ser fabricado por diferentes vias como fundição, forjamento, metalurgia do pó ou manufatura aditiva [2,9].Suas excelentes propriedades advém do controle de sua microestrutura. A alta resistência mecânica da liga é induzida primordialmente pela precipitação das fases endurecedoras e metaestáveis´ (Ni3(Al,Ti), L12) e ´´ (Ni3Nb, D022), sendo a última mais efetiva.…”

Section: Introductionunclassified

Analise Da Morfologia De Carbetos (Ni,ti)c Da Superligas De Niquel 718 Após Processo Termomecânico

Guimarães¹,

Araújo²

2017

Anais Do Enemet - Encontro Nacional De Estudantes De Engenharia Metalúrgica, De Materiais E De Minas

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ResumoA superliga de níquel 718 é uma superliga endurecida por precipitação, com alta resistência mecânica sob condições extremas e ambientes agressivos. Encontra aplicações como componentes críticos para indústrias aeroespacial, óleo e gas e nuclear. Seu alto teor de elementos de liga promove a ocorrência de diversas fases com consequente impacto nas propriedades. O presente trabalho foca na comparação por análise de imagens na morfologia, fração volumétrica, tamanho médio e distribuição de partículas de carbonetos (Nb,Ti)C após duas rotas de processamento termomecânico. Sua quantidade, distribuição e morfologia podem ter um papel em processos de degradação como corrosão e fragilização ao hidrogênio. Portanto, é importante saber como se desenvolve sob diferentes rotas de processamento. Palavras-chave: Superliga 718; Inconel 718; Carboneto; Processamento termomecânico. ANALYSIS OF (NB,TI)C CARBIDE MORPHOLOGY IN NICKEL-BASE SUPERALLOY 718 AFTER THERMOMECHANICAL PROCESSING AbstractNickel base superalloy 718 is a precipitation hardened Ni-base superalloy, with high strength under extreme temperatures and harsh environments. It finds applications as critical components for airspace, oil and gas and nuclear industries. Its high content of allying elements promotes several phases with impact on properties. The present work aims to compare by image analysis the morphology, volume fraction, average size and distribution of (Nb,Ti)C particles after two different routes of thermomechanical processing. Its amount, distribution and morphology can play a role on degradation processes such as corrosion and hydrogen embrittlement. It is, then, important to know how it develops under different processing routes.

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Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors

Cited by 167 publications

References 50 publications

Damage assessment in structural metallic materials for advanced nuclear plants

Damage assessment in structural metallic materials for advanced nuclear plants

In-situ Creep Testing Capability Development for Advanced Test Reactor

Analise Da Morfologia De Carbetos (Ni,ti)c Da Superligas De Niquel 718 Após Processo Termomecânico

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