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Zircaloy 4 Cladding Deformation During Power Reactor Irradiation
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Book Synopsis Zircaloy-4 Cladding Deformation During Power Reactor Irradiation by : DG. Franklin
Download or read book Zircaloy-4 Cladding Deformation During Power Reactor Irradiation written by DG. Franklin and published by . This book was released on 1982 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt: The four primary Zircaloy fuel cladding deformation phenomena--axial elongation, circumferential creep, ovalization, and ridging--have been investigated for fuel irradiated in four modern pressurized water reactors. The axial elongation of fueled and nonfueled rods is examined by a regression fit for dependence on fluence, clad texture, yield stress, applied stress and, for fuel rods, fuel pellet length to diameter ratio. For fueled rods, only fluence and stress are found to be important, although the range of texture data is small. For nonfueled rods, the texture is found to influence elongation.
Book Synopsis Creep of Zirconium Alloys in Nuclear Reactors by :
Download or read book Creep of Zirconium Alloys in Nuclear Reactors written by and published by ASTM International. This book was released on with total page 308 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Zirconium in the Nuclear Industry by :
Download or read book Zirconium in the Nuclear Industry written by and published by ASTM International. This book was released on with total page 490 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Zirconium in the Nuclear Industry by : D. Franklin
Download or read book Zirconium in the Nuclear Industry written by D. Franklin and published by ASTM International. This book was released on 1982 with total page 516 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Temperature and Pressure on the In-Reactor Creepdown of Zircaloy Fuel Cladding by : CV. Dodd
Download or read book Effects of Temperature and Pressure on the In-Reactor Creepdown of Zircaloy Fuel Cladding written by CV. Dodd and published by . This book was released on 1982 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Descriptions and results for seven of the eight in-reactor creepdown tests of Zircaloy fuel cladding, which were part of a joint program between the U.S. Nuclear Regulatory Commission and Energieonderzoek Centrum Nederland, are presented. These tests were conducted to study the behavior of Zircaloy fuel cladding under conditions that approximate those found in an operating pressurized-water power reactor.
Book Synopsis Creep of Zirconium Alloys in Nuclear Reactors by : D. G. Franklin
Download or read book Creep of Zirconium Alloys in Nuclear Reactors written by D. G. Franklin and published by ASTM International. This book was released on 1983 with total page 322 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Zirconium in the Nuclear Industry by : George P. Sabol
Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 1996 with total page 907 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Elements Of Nuclear Reactors by : D.K. Jha
Download or read book Elements Of Nuclear Reactors written by D.K. Jha and published by Discovery Publishing House. This book was released on 2004 with total page 230 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book elements of nuclear reactors has been written to meet the requirement of the student of pass course, honours and post graduate students the subject matter of this book is presented in very straightforward matter. Nuclear reactors is a very important part of nuclear physics, having a broad field, we have try to maintain this field under the small volume according our best adherence. Contents: Interactions of Nuclear Radiation with Matter, Nuclear Reactions, Nuclear Models, Neutrons.
Book Synopsis Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding by : J. O. Barner
Download or read book Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding written by J. O. Barner and published by . This book was released on 1985 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding by : DL. Baty
Download or read book Deformation Characteristics of Cold-Worked and Recrystallized Zircaloy-4 Cladding written by DL. Baty and published by . This book was released on 1984 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermomechanical processing of Zircaloy-4 cladding plays a major role in determining its deformation behavior. Crystallographic texture and the related anisotropy in mechanical properties of Zircaloy-4 have been shown to be affected by different processing paths. In this program, the deformation behavior of four Zircaloy-4 cladding types was evaluated in laboratory and in-reactor studies under typical pressurized-water reactor (PWR) conditions. In particular, the creep behavior, stress-free growth, and mechanical property changes of these materials were examined.
Book Synopsis Zirconium in the Nuclear Industry by : Leo F. P. Van Swam
Download or read book Zirconium in the Nuclear Industry written by Leo F. P. Van Swam and published by ASTM International. This book was released on 1989 with total page 781 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-08 with total page 958 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys by : B. Bourdiliau
Download or read book Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys written by B. Bourdiliau and published by . This book was released on 2010 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zirconium alloys are commonly used in pressurized water reactor as fuel rod cladding tubes. After irradiation and cooling in pool, the spent nuclear fuel assemblies are either transported for wet storage to a devoted site or loaded in suitable casks for dry storage on a nuclear power plant site. During dry transportation or at the beginning of dry storage, at temperatures around 400°C, the cladding experiences a creep deformation under the hoop stress induced by the internal pressure of the fuel rod. During creep, a recovery of the radiation damage can occur that can affect the subsequent mechanical properties. The mechanical behavior of the cladding has been investigated in laboratory on two neutron irradiated cladding materials: fully recrystallized Zr-1 % Nb and stress-relieved Zircaloy-4. Creep tests under internal pressure were conducted at 400 and 420°C. After depressurization and cooling, ring tensile tests were carried out at room temperature. In addition, transmission electron microscopy observations have been performed after testing. The post-creep mechanical response exhibited a decrease of the strength compared to the as-irradiated material. This decrease is associated with a significant recovery of the ductility, which becomes close to the ductility of the unirradiated material. The transmission electron microscopy examinations, conducted on recrystallized Zr-1 % Nb ring samples, revealed that the radiation defects have been annealed. It was also observed that as for the unirradiated material, the deformation occurred homogeneously throughout the grains. No dislocation channeling was observed contrary to the as-irradiated material. These observations explain the recovery of the strength and of the ductility after post-irradiation creep that may also occur during dry transportation or at the beginning of dry storage.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1986 with total page 656 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Heavy Water Moderated Power Reactors by :
Download or read book Heavy Water Moderated Power Reactors written by and published by . This book was released on 1961-07 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Structural Alloys for Nuclear Energy Applications by : Robert Odette
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 673 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.
Book Synopsis Zirconium in the Nuclear Industry by : Gerry D. Moan
Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
