In Chapter–1 of this timely book, radiation damage in vanadium, niobium, molybdenum and tungsten is discussed at the atomic level; treating – for instance - third-stage recovery in terms of self-interstitials being mobile traps for - predominantly - vacancies. Higher recovery stages are treated by using various techniques, such as: electrical resistivity, electron microscopy, positron annihilation spectroscopy and computer simulation - thus revealing vacancy-cluster break-up in stage-V and interstitial cluster annealing in stage-VI.

The study of radiation damage in solids generally has been stimulated by the technological demands of nuclear energy and space research. Professor Thompson's 1969 book discusses the basic atomic mechanisms which give rise to the main effects induced by radiation in metals, since it is in their relatively simple structures that the fundamental processes can be most easily identified. The first part of the book describes the nature of lattice defects in metal crystals. The presentation leads naturally into the discussion of radiation damage in the second part and recognises the important contribution that the study of irradiated metals has made to our general knowledge of defects. The wide coverage of this book includes developments in our understanding of collision cascades, of the clustering of point defects and the behaviour of impurities induced by irradiation.

Studies on the effects of heat-treating and testing environments for the refractory metals have been limited primarily to the unalloyed metals and a few alloys of columbium and molybdenum. Most of this work has relied on compositional changes as a means of assesing the effects of various environments on these materials. It has been shown that all of these materials are subject to contamination or purification in various test environments. The residual gases H2, CO(or N2), and H20, constitute the major sources of contamination when testing columbium and tantalum materials in vacua. Under the same conditions, molybdenum and molybdenum alloys containing carbon and reactive-metal additions are subject to serious decarburization. Nonreactive gaseous atmospheres also cause serious changes in material chemistry, since small quantities of noxious gases are contained in the atmosphere. Several promising methods of circumventing material chemistry changes during various longtime, high-temperature exposures are being used and/or evaluated. (Author).

This report presents the results of progress made during the first year of a three year program on the investigation of swelling mechanisms in refractory metals irradiated at elevated temperatures, i.e. 0.3 T sub m - 0.6 T sub m (where T sub m = melting point in K). The objective of this work is to achieve an understanding of the elevated temperature swelling in these body centered cubic (bcc) metals by a close coupling of theoretical development and experimental verification. Originator supplied keywords include: Swelling, Radiation effects, Ion bombardment, Refractory metals, Theory of swelling, Ion-simulation irradiation.

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.

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