Properties of V-4Cr-4Ti for Application as Fusion Reactor Structural Components PDF Download

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Languages : en
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Languages : en
Pages : 4

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Following previous reports of excellent properties of a laboratory heat of V-4Cr-4Ti, the alloy identified as the primary vanadium-based candidate for application as fusion reactor structural components, a large industrial-scale (500-kg) heat of the alloy was fabricated successfully. The objective of this work is to determine the impact properties of the industrial-scale heat.

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Languages : en
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Languages : en
Pages : 5

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On the basis of excellent properties that were determined for a laboratory-scale heat, V-4Cr-4Ti has been identified previously as the primary vanadium-based candidate alloy for application in fusion reactor structural components. The objective of this work is to produce a large-scale (500-kg) ingot and fabricate various plates and sheets from the ingot, thereby demonstrating a reliable method of fabricating an industrial-scale heat of V-4Cr-4Ti that exhibits excellent properties.

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Languages : en
Pages : 20

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Vanadium alloys exhibit important advantages as a candidate structural material for fusion first-wall/blanket applications. These advantages include high temperature and high wall load capability, favorable safety and environmental features, resistance to irradiation damage, and alloys of interest are readily fabricable. A substantial data base has been developed on laboratory-scale heats of V-Ti, V-Cr-Ti and V-Ti-Si alloys before and after irradiation. Investigations in recent years have focused primarily on compositions of V-(0--15)Cr-(0--20)Ti (0--1)Si. Results from these investigations have provided a basis for identifying a V-4Cr-4Ti alloy as the US reference vanadium alloy for further development. Major results obtained on one production-scale heat and three laboratory heats with compositions of V-(4--5)Cr-(4--5)Ti are presented in this paper. Properties measured were input properties, tensile properties, creep, and radiation effects.

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Category : Aeronautics
Languages : en
Pages : 652

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Author: Robert Odette
Publisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 673

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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.

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Languages : en
Pages : 5

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On the basis of excellent properties that were determined for a laboratory-scale heat, V-4Cr-4Ti has been identified previously as the most promising vanadium-based candidate alloy for application in fusion reactor structural components. The objective of this work is to produce a large-scale (500-kg) ingot of the alloy and fabricate various plates and sheets from the ingot, thereby demonstrating a reliable method of fabricating an industrial-scale heat of V-4Cr-4Ti that exhibits excellent properties. A 500-kg heat of V-4Cr-4Ti, an alloy identified previously as the most promising vanadium-based candidate alloy for application in fusion reactor structural components, has been produced. The ingot was produced by multiple vacuum-arc melting using screened high-quality raw materials of vanadium, chrome, and titanium. Several long bars ≈64 mm in thickness and ≈200 mm in width were extruded from the ingot, and plates and sheets of various thicknesses ranging from 1.0 to 29.2 mm were fabricated successfully from the extruded bars. The chemical composition of the ingot and the secondary fabrication procedures, specified on the basis of the experience and knowledge gained from fabrication, testing, and microstructural characterization of a laboratory-scale heat, were found to be satisfactory. Charpy-impact tests showed that mechanical properties of the production-scale heat are as good as those of the laboratory-scale heat. This demonstrates a method of reliable fabrication of industrial-scale heats of V-4Cr-4Ti that exhibit excellent properties. 14 refs., 1 fig., 1 tab.

Author: Pascal Yvon
Publisher: Woodhead Publishing
ISBN: 0081009127
Category : Technology & Engineering
Languages : en
Pages : 686

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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

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Languages : en
Pages : 13

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One property of vanadium-base alloys that is not well understood in terms of their potential use as fusion reactor structural materials is the effect of simultaneous generation of helium and neutron damage. In the present Dynamic Helium Charging Experiment (DHCE), helium was produced uniformly in the specimen at linear rates of (almost equal to) 0.4 to 4.2 appm helium/dpa by the decay of tritium during irradiation to 18--31 dpa at 425--600 C in Li-filled capsules in a sodium-cooled fast reactor. This paper presents results of postirradiation examination and tests of microstructure and mechanical properties of V-5Ti, V-3Ti-1Si, V-8Cr-6Ti, and V-4Cr-4Ti (the latter alloy has been identified as the most promising candidate vanadium alloy). Effects of helium on tensile strength and ductility were insignificant after irradiation and testing at> 420 C. However, postirradiation ductilities at 250 C were higher than those of the non-DHCE specimens (