Download or read book Austenitic Stainless Steel as a Fuel Element Cladding written by Alton Schmitt and published by . This book was released on 1959 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Experience with Stainless Steel as a Fuel Cladding Material in Water cooled Power Reactor Applications written by T. J. Pashos and published by . This book was released on 1963 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Chemical Interaction of Metallic Fuel with Austenitic and Ferritic Stainless Steel Cladding written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The combination of metallic fuel and stainless steel cladding in a fuel element forms a complex multicomponent diffusion couple at elevated temperatures. Interdiffusion of fuel and cladding components can in principle lead to several phenomena that could affect the reliable performance of a fuel element. These phenomena include the formation of strength reducing diffusion zones in the cladding, intergranular penetration of fuel components into the cladding, and the formation of compositional zones with melting points below the anticipated operating temperatures. A series of ex-reactor tests were performed to assess and study this potential problem in fuel elements consisting of U-Zr, U-Pu-Zr fuel clad in Ti stabilized austenitic stainless steel (D9) and ferritic stainless steel (HT-9). Diffusion couples of various combinations of fuel and the different steels were annealed at temperatures ranging from 650°C to 800°C for up to 3000 h in an argon atmosphere. The post-test analysis of the diffusion couples included: metallographic examinations, scanning electron microscopy, and scanning Auger microscopy.

Download or read book Some Observations of the Intergranular Corrosion of Irradiated Type 304 Stainless Steel written by E. L. Long (Jr.) and published by . This book was released on 1964 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Development of Ferritic Stainless Steel written by W. K. Barney and published by . This book was released on 1958 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Review of Compatibility of IFR Fuel and Austenitic Stainless Steel written by and published by . This book was released on 1996 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Interdiffusion experiments have been conducted to investigate the compatibility of various austenitic stainless steels with U-Pu-Zr alloys, which are alloys to be employed as fuel for the Integral Fast Reactor being developed by Argonne National Laboratory. These tests have also studied the compatibility of austenitic stainless steels with fission products, like the minor actinides (Np and Am) and lanthanides (Ce and Nd), that are generated during the fission process in an IFR. This paper compares the results of these investigations in the context of fuel-cladding compatibility in IFR fuel elements, specifically focusing on the relative Interdiffusion behavior of the components and the types of phases that develop based on binary phase diagrams. Results of Interdiffusion tests are assessed in the light of observations derived from post-test examinations of actual irradiated fuel elements.

Download or read book Austenitic Stainless Steel for High Temperature Applications written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This invention describes a composition for an austenitic stainless steel which has been found to exhibit improved high temperature stress rupture properties. The composition of this alloy is about (in wt. %): 12.5 to 14.5 Cr; 14.5 to 16.5 Ni; 1.5 to 2.5 Mo; 1.5 to 2.5 Mn; 0.1 to 0.4 Ti; 0.02 to 0.08 C; 0.5 to 1.0 Si; 0.01 maximum, N; 0.02 to 0.08 P; 0.002 to 0.008 B; 0.004-0.010 S; 0.02-0.05 Nb; 0.01-0.05 V; 0.005-0.02 Ta; 0.02-0.05 Al; 0.01-0.04 Cu; 0.02-0.05 Co; 0.03 maximum, As; 0.01 maximum, O; 0.01 maximum, Zr; and with the balance of the alloy being essentially iron. The carbon content of the alloy is adjusted such that wt. % Ti/(wt. % C+wt. % N) is between 4 and 6, and most preferably about 5. In addition the sum of the wt. % P+wt. % B+wt. % S is at least 0.03 wt. %. This alloy is believed to be particularly well suited for use as fast breeder reactor fuel element cladding.

Download or read book Considerations on the Media for Decay Storage of Fuel Elements written by W. K. Winegardner and published by . This book was released on 1968 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report was prepared in response to a Fast Flux Test Facility (FFTF) Division request for information and recommendations concerning the decay storage of irradiated fuel elements. The report first summarizes information concerning irradiated fuel element storage techniques. This summary is followed by a discussion of information related to fuel cladding corrosion problems that conceivably could result from decay storage after in-core exposure. Finally, all of the information, obtained primarily by literature review, is used as the basis for recommendations concerning storage media. The work was prompted by concern over possible loss of fuel element cladding integrity during decay storage in air or water. The concern ranges from effects that could hinder fuel examination to those that could result in local regions of cladding penetration or even failure while handling fuel. This report is primarily related tot he latter type of effect, since the facility is viewed simply as a cell or basin where fuel elements can safely be stored prior to chemical processing.

Download or read book Hearings written by United States. Congress Senate and published by . This book was released on 1969 with total page 1456 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Hearings Reports and Prints of the Senate Committee on Appropriations written by United States. Congress. Senate. Committee on Appropriations and published by . This book was released on 1969 with total page 1464 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 1980 with total page 360 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 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Residual Elements on Properties of Austenitic Stainless Steels written by and published by . This book was released on 1967 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1971 with total page 1330 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Liquid Metal Fast Breeder Reactors 1962 1971 written by U.S. Atomic Energy Commission and published by . This book was released on 1976 with total page 722 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 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Comprehensive Nuclear Materials written by Todd R Allen and published by Elsevier. This book was released on 2011-05-12 with total page 3552 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants