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Irradiation Swelling Phase Reversion And Intergranular Cracking Of U 10 Wt Mo Fuel Alloy
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Book Synopsis Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 Wt % Mo Fuel Alloy by : R. M. Willard
Download or read book Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 Wt % Mo Fuel Alloy written by R. M. Willard and published by . This book was released on 1965 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis IRRADIATION SWELLING, PHASE REVERSION, AND INTERGRANULAR CRACKING OF U-10 Wt.% Mo FUEL ALLOY. by :
Download or read book IRRADIATION SWELLING, PHASE REVERSION, AND INTERGRANULAR CRACKING OF U-10 Wt.% Mo FUEL ALLOY. written by and published by . This book was released on 1965 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Swelling, Phase Reversion, and Intergranualr Cracking of U-10 Wt % Mo Fuel Alloy by : R. M. Willard
Download or read book Irradiation Swelling, Phase Reversion, and Intergranualr Cracking of U-10 Wt % Mo Fuel Alloy written by R. M. Willard and published by . This book was released on 1965 with total page 0 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 1975-03 with total page 988 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Materials written by and published by . This book was released on 1965 with total page 288 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Reports Received by Division of Technical Information Extension by : U.S. Atomic Energy Commission. Division of Technical Information
Download or read book Reports Received by Division of Technical Information Extension written by U.S. Atomic Energy Commission. Division of Technical Information and published by . This book was released on with total page 932 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government-wide Index to Federal Research & Development Reports by :
Download or read book Government-wide Index to Federal Research & Development Reports written by and published by . This book was released on 1965 with total page 886 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1965 with total page 364 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comprehensive Nuclear Materials by : Todd R Allen
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
Book Synopsis Transactions of the American Nuclear Society by : American Nuclear Society
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1964 with total page 614 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Irradiation Swelling of Uranium and Uranium Alloys by : Gordon G. Bentle
Download or read book Irradiation Swelling of Uranium and Uranium Alloys written by Gordon G. Bentle and published by . This book was released on 1961 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis U.S. Government Research & Development Reports by :
Download or read book U.S. Government Research & Development Reports written by and published by . This book was released on 1965 with total page 1318 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Quarterly Technical Progress Report by :
Download or read book Quarterly Technical Progress Report written by and published by . This book was released on 1965 with total page 298 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Announcements by :
Download or read book Government Reports Announcements written by and published by . This book was released on 1965 with total page 978 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Experimental and Calculated Swelling Behavior of U-10 Wt.% Mo Under Low Irradiation Temperatures by :
Download or read book Experimental and Calculated Swelling Behavior of U-10 Wt.% Mo Under Low Irradiation Temperatures written by and published by . This book was released on 1998 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: SEM micrographs of U-10 wt.% Mo irradiated at low temperature in the ATR to about 40 at. % burnup show the presence of cavities. We have used a rate-theory-based model to investigate the nucleation and growth of cavities during low-temperature irradiation of uranium-molybdenum alloys in the presence of irradiation-induced interstitial-loop formation and growth. In addition, the evolution of forest dislocations was calculated based on dislocation loop growth and simultaneous climb and glide of unfaded loops. Consolidation of the dislocation structure takes into account capture of interstitial dislocation loops and annihilation of adjacent dislocations, as well as loss to grain boundaries. A di-interstitial is assumed to be the nucleus of a dislocation loop. Cavities are nucleated when two gas atoms come together in the presence of at least one vacancy. Cavity growth occurs by the influx of gas atoms and/or vacancies. In turn, the free interstitial concentration, and thus (due to recombination) the free-vacancy concentration, depends on the dislocation density. Bias-driven growth of cavities can lead to substantial swelling of the alloy (void swelling). However, our calculations indicate that the swelling mechanism in the U-10 wt.% Mo alloy at low irradiation temperatures is fission gas driven. The calculations also indicate that the observed bubbles must be associated with a sub-grain structure. Calculated swelling and bubble-size-distribution are compared with irradiation data.
Book Synopsis Government Reports Annual Index by :
Download or read book Government Reports Annual Index written by and published by . This book was released on 1965 with total page 480 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Effects of Second-Phase Particles on Irradiation Swelling of Austenitic Alloys by : WK. Appleby
Download or read book Effects of Second-Phase Particles on Irradiation Swelling of Austenitic Alloys written by WK. Appleby and published by . This book was released on 1973 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results are described from the investigation of swelling caused by fast-neutron-induced void formation in stainless steel fuel cladding and high-nickel alloys irradiated in fast flux (EBR-II) to fluences up to 7.3 x 1022 n/cm2, E > 0.1 MeV. Immersion density measurements of swelling gave results ranging from a volume increase of 10 percent in solution-annealed Type 347 stainless steel to a small densification in Inconel-625. Transmission electron microscopy investigations revealed that the extent of void formation in Types 316 and 347 stainless steels, Incoloy-800, and Hastelloy-X was related to the degree of intragranular precipitation (principally carbides), whereas the Ni3 Cb precipitation in Inconel-625 had apparently inhibited void formation altogether. It is concluded that precipitate particles can play a major role in determining the extent of void formation in austenitic alloys during neutron irradiation, and in the optimum morphology (a high concentration of closely spaced, small and possibly coherent particles) they offer promise of largely inhibiting void formation and swelling.
