Effects of Radiation on Structural Materials PDF Download

Author: James A. Sprague
Publisher: ASTM International
ISBN: 9780803103276
Category : Technology & Engineering
Languages : en
Pages : 700

View

Book Description

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 11

View

Book Description
An evaluation of proton and neutron damage to aluminum, stainless steel, nickel alloys, and various aluminum alloys has been performed. The proton studies were conducted at energies of 200 MeV, 800 MeV, and 23.5 GeV. The proton studies consisted of evaluation and characterization of proton-irradiated window/target materials from accelerators and comparison to nonirradiated archival materials. The materials evaluated for the proton irradiations included 99.9999 wt% aluminum, 1100 aluminum, 5052 aluminum, 304 stainless steel, and inconel 718. The neutron damage research centered on 6061 T-6 aluminum which was obtained from a control-rod follower from the Brookhaven National Laboratory's (BNL) High Flux Beam Reactor (HFBR). This material had received thermal neutron fluence up to (approximately)4 x 1023 n/cm2. The possible effects of thermal-to-fast neutron flux ratios are discussed. The increases in tensile strength in the proton-irradiated materials is shown to be the result of atomic displacements. These displacements cause interstitials and vacancies which aggregate into defect clusters which result in radiation hardening of the materials. Production of gas (helium) in the grain boundaries of proton irradiated 99.9999 wt% aluminum is also discussed. The major factor contributing to the mechanical-property changes in the neutron-irradiated 6061 T-6 aluminum is the production of transmutation products formed by interactions of the aluminum with thermal neutrons. The metallurgical and mechanical-property evaluations for the research consisted of electron microscopy (both scanning and transmission), tensile testing, and microhardness testing.

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

View

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.

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

View

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

Author: David Kramer
Publisher:
ISBN:
Category :
Languages : en
Pages : 684

View

Book Description

Author: Yongqiang Wang
Publisher: MDPI
ISBN: 303936362X
Category : Science
Languages : en
Pages : 196

View

Book Description
The complexity of radiation damage effects in materials that are used in various irradiation environments stems from the fundamental particle–solid interactions and the subsequent damage recovery dynamics after the collision cascades, which involves multiple length and time scales. Adding to this complexity are the transmuted impurities that are unavoidable from accompanying nuclear processes. Helium is one such impurity that plays an important and unique role in controlling the microstructure and properties of materials used in fast fission reactors, plasma-facing and structural materials in fusion devices, spallation neutron target designs, actinides, tritium-containing materials, and nuclear waste. Their ultra-low solubility in virtually all solids forces He atoms to self-precipitate into small bubbles that become nucleation sites for further void growth under radiation-induced vacancy supersaturations, resulting in material swelling and high-temperature He embrittlement, as well as surface blistering under low-energy and high-flux He bombardment. This Special Issue, “Radiation Damage in Materials—Helium Effects”, contains review articles and full-length papers on new irradiation material research activities and novel material ideas using experimental and/or modeling approaches. These studies elucidate the interactions of helium with various extreme environments and tailored nanostructures, as well as their impact on microstructural evolution and material properties.

Author: Melvin L. Bleiberg
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 940

View

Book Description

Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 652

View

Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.

Author: J. Koutský
Publisher: Elsevier
ISBN: 1483291626
Category : Technology & Engineering
Languages : en
Pages : 362

View

Book Description
Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analysing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials. This monograph will be of great value to postgraduate students in nuclear engineering and materials science, and for designers and research workers in nuclear energy.

Author: Naval Research Laboratory (U.S.)
Publisher:
ISBN:
Category : Naval research
Languages : en
Pages : 52

View

Book Description