Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures

Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures PDF Author: Metals Society
Publisher: Ashgate Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 276

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Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures

Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures PDF Author: Metals Society
Publisher: Ashgate Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 276

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Austenitic Stainless Steels

Austenitic Stainless Steels PDF Author: P. Marshall
Publisher: Springer Science & Business Media
ISBN: 9780853342779
Category : Technology & Engineering
Languages : en
Pages : 458

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MiCon 86

MiCon 86 PDF Author: B. L. Bramfitt
Publisher: ASTM International
ISBN: 0803109857
Category : Alloys
Languages : en
Pages : 324

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Mechanical and Thermal Behaviour of Metallic Materials

Mechanical and Thermal Behaviour of Metallic Materials PDF Author: G. Caglioti
Publisher: Elsevier
ISBN: 0080983839
Category : Technology & Engineering
Languages : en
Pages : 517

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Book Description
Mechanical and Thermal Behaviour of Metallic Materials

Corrosion of Austenitic Stainless Steels

Corrosion of Austenitic Stainless Steels PDF Author: H S Khatak
Publisher: Woodhead Publishing
ISBN: 9781855736139
Category : Science
Languages : en
Pages : 436

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Book Description
This comprehensive study covers all types of corrosion of austenitic stainless steel. It also covers methods for detecting corrosion and investigating corrosion-related failure, together with guidelines for improving corrosion protection of steels. Details all types of corrosion of austenitic stainless steel Covers methods for detecting corrosion and investigating corrosion-related failure Outlines guidelines for improving corrosion protection of steels

Proceedings of the 10th International Conference on Fracture Fatigue and Wear

Proceedings of the 10th International Conference on Fracture Fatigue and Wear PDF Author: Magd Abdel Wahab
Publisher: Springer Nature
ISBN: 9811978085
Category : Science
Languages : en
Pages : 124

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Book Description
This book gathers a selection of peer-reviewed papers presented at the 10th International Conference on Fracture Fatigue and Wear (FFW 2022), held in the city of Ghent, Belgium, on August 2–3, 2022. The contributions, prepared by international scientists and engineers, cover the latest advances in and innovative applications of fracture mechanics, fatigue of materials, tribology, and wear of materials. In addition, they discuss industrial applications and cover theoretical and analytical methods, numerical simulations, and experimental techniques. The book is intended for academics, including graduate students and researchers, as well as industrial practitioners working in the areas of fracture fatigue and wear.

Structural Materials for Generation IV Nuclear Reactors

Structural Materials for Generation IV Nuclear Reactors PDF Author: Pascal Yvon
Publisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686

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Book Description
Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area

High Temperature Fatigue

High Temperature Fatigue PDF Author: R.P. Skelton
Publisher: Springer Science & Business Media
ISBN: 940093453X
Category : Technology & Engineering
Languages : en
Pages : 330

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Book Description
About 35 years ago, thermal fatigue was identified as an important phenomenon which limited the lifetime of high temperature plant. In the intervening years many investigations have been carried out, primarily to give guidance on likely endurance (especially in the presence of time dependent deformation) but latterly, with the introduction of sophisticated testing machines, to provide knowledge of the underlying mechanisms of failure. A previous edited book (Fatigue at High Temperature, Elsevier Applied Science Publishers, 1983) summarised the state-of-the-art of high temperature fatigue testing and examined the factors influencing life, such as stress state, environment and microstructural effects. It also considered, in some detail, cyclic crack growth as a more rigorous approach to life limitation. The aim of the present volume (which in style and format follows exactly the same lines as its predecessor) is once again to pursue the desire to translate detailed laboratory knowledge into engineering design and assessment. There is, for example, a need to consider the limitations of the laboratory specimen and its relationship with engineering features. Many design procedures still rely on a simple endurance approach based on failure of a smooth specimen, and this is taken to indicate crack initiation in the component. In this volume, therefore, crack propagation is covered only incidentally, emphasis being placed instead on basic cyclic stress strain properties, non-isothermal behaviour, metallography, failure criteria and the need for agreed testing procedures.

Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures

Mechanical Behaviour and Nuclear Applications of Stainless Steel at Elevated Temperatures PDF Author:
Publisher:
ISBN:
Category : Stainless steel
Languages : en
Pages : 0

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Book Description


Structural Alloys for Nuclear Energy Applications

Structural Alloys for Nuclear Energy Applications PDF Author: Robert Odette
Publisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 676

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Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.