Download or read book High Temperature Helium Embrittlement in Irradiated Stainless Steel written by Awadalla Messiah Awadalla and published by . This book was released on 1981 with total page 242 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book An Electron Microscope Investigation of the High temperature Embrittlement of Irradiated Stainless Steels written by A.F. Rowcliffe and published by . This book was released on 1966 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Solutions to the Problems of High Temperature Irradiation Embrittlement written by W. R. Martin and published by . This book was released on 1967 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of irradiation on high-temperature mechanical properties of structural materials is described using Type 304 stainless steel as an example. The general effect is one in which the grain-boundary fracture process, but not the deformation process, is affected. The data suggest the primary cause to be helium generated from (n,?) reactions. Several metallurgical techniques for improving the ductilities of irradiated alloys are suggested, and experimental data on Type 304 stainless steel are given for which the degree of improvement is demonstrated.
Download or read book Irradiation Effects in Stainless Steels at High Temperatures written by and published by . This book was released on 1965 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book On the Role of Helium in High Temperature Embrittlement of Irradiated Austenitic Steels written by W. Kesternich and published by . This book was released on 1990 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Helium that is produced by nuclear transmutations can cause severe degradation of the mechanical properties in structural components of fusion and fast fission reactors. For studying the mechanisms of irradiation embrittlement, the helium effects have been simulated by helium implantation from cyclotrons or by making use of (n,?) reactions from thermal neutron fluxes. As is discussed in the present paper, the results from neutron irradiations and helium implantations are contradictory with respect to the helium levels at which helium embrittlement appears. To study the combined effect of helium and neutron irradiation on embrittlement, two titanium stabilized austenitic steels of identical composition, with the exception of their boron content of 40 and 2 ppm, respectively, have been neutron-irradiated at 845 K to thermal neutron fluences of 2.6 x 1025 n/m2. The precipitate and helium bubble microstructure has been quantitatively characterized by transmission electron microscopy (TEM) and has been correlated with the embrittlement behavior, studied in post-irradiation creep experiments at 973 K. Contrary to the expectation the material with the lower helium content was found to exhibit the higher reduction in creep strength after irradiation.
Download or read book Irradiation Effects in Structural Alloys for Thermal and Fast Reactors written by and published by ASTM International. This book was released on with total page 437 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Effects of Radiation on Structural Metals written by Books on Demand and published by ASTM International. This book was released on 1967 with total page 723 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Heat Treatment and Irradiation on the High Temperature Tensile Properties of Austenitic Stainless Steels written by D. R. Harries and published by . This book was released on 1967 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of boron content and heat treatment on the microstructures, high temperature tensile properties, and fracture behavior of unirradiated and irradiated 18Cr-10Ni-Cb stabilized austenitic steel have been investigated. The location and distribution of the boron were determined using an autoradiographic technique. The results support the view that boron has a dual role in the irradiation-induced high temperature embrittlement of austenitic steels in that the helium formed by the 10B(n,?)Li7 reaction is detrimental but that boron itself exerts a beneficial effect.
Download or read book High temperature Irradiation of Metals and Graphite in Flowing Helium written by Neil E. Miller and published by . This book was released on 1960 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the coolant-core evaluation studies in an early phase of the Maritime Gas-Cooled Reactor program, nickel. K-Monel, niobium-1 wt.% zirconium, and graphite were irradiated in a convective flow of helium. A capsule of novel design was used to study the corrosion of the metals at 1500 and 960 ction prod- F in a 243-hr BRR experiment. Four heliumfilled quartz tori, containing the specimens, were encapsulated in a stainless steel capsule. A convective flow of helium was maintained in the closed tori by heating one leg of each torus to 1500 and the other at 960-F. Zirconium foilwas placed in two of the tori to getter gaseous impurities. No attack of the nickel and niobium-1 wt.% zirconium was observed at either temperature. Metallographic examination did show a 1 to 2.5- mil attack of the K-Monel at 1500 ction prod- F in a torus containing no getter. (auth).
Download or read book Effects of Neutron Irradiation and Fatigue on Ductility of Stainless Steel DIN 1 4948 written by MI. de Vries and published by . This book was released on 1979 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Test specimens of stainless steel DIN 1.4948, which is similar to AISI Type 304, have been irradiated at 723 and 823 K up to fluences of 1 x 1023 neutrons (n)•m-2 and 5 x 1024 n.m-2 (E > 0.1 MeV). These are representative conditions for the reactor vessel and inner components of the liquid metal fast breeder reactor SNR-300 after 16 years of operation. High-temperature (723 to 1023 K) tension tests at strain rates (?) from 10-7 to 10 s-1 show a considerable decrease of tensile ductility. The extent depends on helium content, test temperature, and strain rate. The atomic helium fractions of 3 x 10-7 and 7 x 10-6 result from the reactions of thermal neutrons with the 14 ppm boron present in the steel. Helium embrittlement sets in at strain rates below 1 to 10 s-1 (the range of interest for Bethe-Tait accident analyses). A minimum total elongation value of 6 percent is shown at 923 K. The postirradiation fatigue life is reduced by up to about 50 percent due to intergranular cracking. The combination of irradiation and fatigue causes a decrease of ductility after a smaller number of prior fatigue cycles than in the case of unirradiated material.
Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effects of Helium on High temperature Ductility of Sandvik 12r72hv and Inco In 744x written by D. Kramer and published by . This book was released on 1970 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book MiCon 86 written by B. L. Bramfitt and published by ASTM International. This book was released on 1988 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Fusion Energy Update written by and published by . This book was released on 1980 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
