Download or read book Microstructural Effects on the Irradiation Growth of Zr 2 5Nb written by JD. Parker and published by . This book was released on 1987 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation growth tests at 553 K and a fast (E > 1.6 x 10-13 J) neutron flux of about 6.5 x 1017 n m-2s-1 were performed on specimens of Zr-2.5Nb pressure tubes to a neutron fluence of 3.5 x 1025 n m-2. The tubes were produced by different routes designed to change texture, grain shape, and dislocation density, but X-ray diffraction studies showed only minor changes in texture and dislocation density. However, electron microscopy revealed marked differences in dislocation substructure and second-phase distribution.
Download or read book Effects of Microstructural Factors on Irradiation Growth in Zirconium Niobium Alloys written by N. Sadaoka and published by . This book was released on 1989 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: The irradiation growth mechanism of Zr-Nb alloys has been evaluated on the basis of a growth model in which point defect parameters obtained by molecular dynamics are used.
Download or read book An overview of microstructural and experimental factors that affect the irradiation growth behavior of zirconium alloys written by V. Fidleris and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Growth in Zr 2 5Nb written by RG. Fleck and published by . This book was released on 1984 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Pressure tube elongation in CANDU (CANada Deuterium Uranium) reactors occurs mainly as a result of irradiation growth and may limit the useful lifetime of the pressure tubes. The object of this investigation was to examine the effects of microstructural variation on the irradiation growth rate as part of a pressure tube development program. Three modifications of Zr-2.5Nb material have been irradiated at 553 K to high fast fluences of 3 x 1025 n/m2 in the Dido reactor at the United Kingdom Atomic Energy Authority Harwell, and the irradiation growth was measured at preselected fluences up to the highest fluence.
Download or read book Oxidation and the Testing of Turbine Oils written by Cyril A. Migdal and published by ASTM International. This book was released on 2008 with total page 929 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work presents papers from a December 2005 symposium held in Norfolk, Virginia, and sponsored by ASTM Committee D2 on Petroleum Products and Lubricants and its Subcommittees D02.09 on Oxidation and D02.C0 on Turbine Oils. Contributors include equipment manufacturers, end users, lubricant producers, lubricant additive suppliers, test equipment manufacturers, and standard test method developers. They share information on industry trends, evolving technologies, and changing equipment designs and operating conditions, with a focus on how these factors impact oxidation. Some topics covered include turbine oil performance limits, a new form of the rotating pressure vessel oxidation test, and degradation mechanisms leading to sludge and varnish in modern turbine oil formulations. B&w photos are included. There is no subject index. Migdal is affiliated with Chemtura Corporation.
Download or read book Zirconium in the Nuclear Industry written by and published by ASTM International. This book was released on with total page 849 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Creep and Growth Behavior and Microstructural Evolution of Advanced Zr Base Alloys written by A. Soniak and published by . This book was released on 2000 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper deals with the irradiation-induced changes in the microstructure of FRAMATOME advanced Zr-base alloys and the correlations with their irradiation creep and growth behavior. The first part is dedicated to experimental irradiations performed at 280 and 350°C in a CEA metallurgical test reactor (Siloé, 1 to 1018 n/m2 s, E > 1 MeV) on stress-relieved (SRA) and recrystallized (RXA) low-tin Zircaloy-4 and two advanced RXA materials (Alloy 4 (M4): Zr-SnFeV, and Alloy 5 (M5): Zr-NbO), which are proposed for fuel rod cladding applications in PWRs. The irradiation creep results confirm the improved behavior of RXA Zy-4, M4, and M5 in comparison to that of SRA Zy-4. Similar trends are observed for irradiation growth, the SRA Zy-4 exhibiting a quasi-linear behavior with increasing fluence while RXA alloys undergo an early saturation phenomenon. Among RXA materials, M5 has the higher irradiation growth resistance. These creep and growth results at moderate neutron fluences (
Download or read book Zirconium in the Nuclear Industry written by D. G. Franklin and published by ASTM International. This book was released on 1984 with total page 866 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr 2 5Nb Pressure Tubing written by L. Walters and published by . This book was released on 2014 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt: Creep experiments have been performed on biaxially stressed 10 mm diameter Zr-2.5Nb capsules. As the pressurized capsules were obtained from micro-pressure tubes, which were fabricated by the same process as CANDU power reactor pressure tubes, they have a similar microstructure to that of the full-size tubes. The experiments were performed in the OSIRIS test reactor at nominal operating temperatures ranging from 553 and 613 K in fast neutron fluxes up to 2 x 1018 n.m-2.s-1 (E > 1 MeV). Diametral and axial strains are reported as functions of fluence for specimens internally pressurized to hoop stresses from 0 to 160 MPa and irradiated to 26.5 dpa. The effects of microstructure, temperature, and cold work on irradiation creep are shown. The analysis of OSIRIS data combined with data from in-service CANDU tubes has revealed some significant observations regarding pressure tube deformation: (i) that irradiation creep anisotropy varies with temperature, (ii) texture appears to have a more significant effect on axial creep than on diametral creep, (iii) diametral strain appears to be strongly dependent on grain size and aspect ratio, and (iv) that whereas cold-work correlates with the axial creep of the capsules, there appears to be no statistically significant dependence of diametral creep on cold-work.
Download or read book Irradiation Induced Growth and Microstructure Evolution of Zr 1 2Sn 1Nb 0 4Fe Under Neutron Irradiation to High Doses written by GP. Kobylyansky and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zirconium alloy components subjected to long-term operation and high doses in thermal reactors need to be highly irradiation resistant to provide integrity of components, primarily, their geometrical sizes. Transmission and scanning electron microscopy, energy dispersive X-ray microanalysis used to investigate thin foils and extraction replicas of irradiated zirconium, Zr-1Nb (E110) and Zr-1.2Sn-1Nb-0.4Fe (E635) alloys allowed us to analyze the evolution of their microstructure under neutron irradiation. The experimental irradiations that were conducted at 350°C to 1027 n/m2 (E >= 0.1 MeV) show that the most irradiation resistant alloy proved to be a multicomponent E635 alloy. It is not essentially subject to growth. Dislocation structure and phase composition were studied as interrelated to different stages of irradiation induced growth. The accelerated growth correlates with a high density of basal -- plane c-component dislocations.
Download or read book The Effect of Temperature on the Irradiation Growth of Cold Worked Zr 2 5 Nb written by RA. Holt and published by . This book was released on 1989 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Specimens of cold-worked Zr-2.5% Nb pressure tube material fabricated by several different routes have been irradiated unstressed in the Dido reactor at Atomic Energy Research Establishment (AERE) Harwell to fluences up to 7.5 x 1025 n/m2, E & 1 MeV (about 18 dpa). Their irradiation growth behavior has been investigated as a function of temperature in the range 553 to 623 K.
Download or read book Microstructure Evolution in Zr Alloys During Irradiation written by M. Griffiths and published by . This book was released on 2008 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: The performance of zirconium alloys in BWR, PWR, and PHWR nuclear reactors is dependent on the microstructure. Accordingly, the characterization of the microstructure is an integral part of any study conducted to develop models for in-reactor performance. Although the as-fabricated microstructure (texture, grain size, dislocation density, and phase or precipitate distribution) determines the basic physical properties of a given component, there are changes that occur during irradiation that can have a significant effect on these properties. Microstructures that illustrate specific features of the radiation damage that forms in Zr alloys will be illustrated and discussed in terms of the dose, dose rate, and impurity factors that are applicable.
Download or read book Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth written by AV. Tselischev and published by . This book was released on 2002 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: The studies of the dislocation structure, phase, and microchemical compositions of alloy Zr-1Nb-1.2Sn-0.35Fe (E635) and its modifications containing Fe from 0.15 to 0.65% were carried out before and after research reactor irradiation at ~350°C to maximal fluence of ~1027 m-2 (E > 0.1 MeV) and at ~60°C. The size and concentration of the a-type loops depend on the alloy composition and fluence and saturate even at low doses (1 dpa). The evolution of the c-component dislocation structure in recrystallized alloys of E365 type is determined by the chemical and phase compositions of alloys specifically, by the Fe/Nb ratio and the threshold dose, and is consistent with the irradiation growth strain acceleration. In E635 alloy containing 0.15%Fe the accelerated growth is observed after the dose of 15 dpa and is attended with the evolution of the c dislocation structure which is similar to Zr-1Nb (E110) alloy behavior. The irradiation induced growth of E635 type alloy containing 0.65% Fe is similar to that of E635 having the normal composition; no
Download or read book Materials Ageing and Degradation in Light Water Reactors written by K L Murty and published by Elsevier. This book was released on 2013-02-18 with total page 441 pages. Available in PDF, EPUB and Kindle. Book excerpt: Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials' ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. - Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors - Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection - Chapters also focus on material management strategies
Download or read book Microstructure dependence of irradiation Creep and growth of zirconium alloys written by R. A. Holt and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Modeling Irradiation Damage in Zr 2 5Nb and Its Effects on Delayed Hydride Cracking Growth Rate written by M. Griffiths and published by . This book was released on 2014 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zr-2.5Nb is a dual-phase alloy consisting of an hcp (?) phase containing up to 1 wt. % Nb and a bcc (?) phase containing about 20 wt. % Nb. The ? phase constitutes the majority of the material volume. For in-service Zr-2.5Nb CANDU pressure tubes, the structures of both the ? and ? phases evolve as a result of the effects of irradiation and operating temperature: dislocation loop formation in the ? phase and decomposition or reconstitution of the ? phase. X-ray diffraction data are used to study the irradiation damage (represented by the integral breadth of hcp diffraction peaks and the lattice parameter of the ? phase). This evolution of the microstructure must be modeled as a function of operating conditions so that the state of the microstructure of in-service pressure tubes can be predicted. Delayed hydride cracking (DHC) growth rates in Zr-2.5Nb CANDU pressure tube material also depends on the state of the microstructure. In this paper, it is shown that the majority of the DHC growth rate changes can be ascribed to thermal and irradiation effects on the microstructure.
Download or read book Irradiation Growth of Zirconium Alloys written by JY. Ren and published by . This book was released on 1994 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Experimental investigation of irradiation growth on annealed Zircaloy-4 and 20% to 50% cold-worked Zr-2.5wt%Nb specimens with stress relief has been carried out. The specimens are irradiated in a heavy water reactor at 610 K to 4.2 x 1024 n/m2 (E > 1.0 MeV). The growth strains increase linearly with fluence. The saturation of growth is not observed for all specimens. The difference of growth behavior between two kinds of Zircaloy-4 tube may be associated with the content of minor alloying elements and impurities that influence the microstructure evolution under irradiation.
