Zirconium in Nuclear Applications
Author : J. H. Schemel
Publisher : ASTM International
Page : 544 pages
File Size : 19,23 MB
Release : 1974
Category : Science
ISBN : 9780803107571
Author : J. H. Schemel
Publisher : ASTM International
Page : 544 pages
File Size : 19,23 MB
Release : 1974
Category : Science
ISBN : 9780803107571
Author : Schemel JH.
Publisher : ASTM International
Page : 532 pages
File Size : 16,3 MB
Release : 1974
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Page : 526 pages
File Size : 28,44 MB
Release : 1974
Category : Zirconium
ISBN :
Author : Robert Odette
Publisher : Newnes
Page : 676 pages
File Size : 27,85 MB
Release : 2019-08-15
Category : Technology & Engineering
ISBN : 012397349X
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.
Author : A. D. Schwope
Publisher :
Page : 20 pages
File Size : 39,35 MB
Release : 1955
Category : Nuclear reactors
ISBN :
Author : D. G. Franklin
Publisher : ASTM International
Page : 866 pages
File Size : 44,45 MB
Release : 1984
Category : Science
ISBN : 9780803102705
Author : George P. Sabol
Publisher : ASTM International
Page : 953 pages
File Size : 11,48 MB
Release : 2000
Category : Microstructure
ISBN : 0803124996
Author : Craig M. Eucken
Publisher : ASTM International
Page : 794 pages
File Size : 50,89 MB
Release : 1991
Category : Nuclear fuel claddings
ISBN : 080311463X
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Author : Michael Vasily Glazoff
Publisher :
Page : 0 pages
File Size : 31,60 MB
Release : 2015
Category : Nuclear fuel claddings
ISBN :
In the post-Fukushima world, thermal and structural stability of materials under extreme conditions is an important issue for the safety of nuclear reactors. Because the nuclear industry will continue using zirconium (Zr) cladding for the foreseeable future, it becomes critical to gain a fundamental understanding of several interconnected problems. First, what are the thermodynamic and kinetic factors affecting oxidation and hydrogen pick-up by these materials at normal, off-normal conditions, and in long-term storage? Secondly, what protective coatings could be used in order to gain valuable time at off-normal conditions (temperature exceeds ~1200°C (2200°F)? Thirdly, the kinetics of the coating's oxidation must be understood. Lastly, one needs automated inspection algorithms allowing identifying cladding's defects. This work attempts to explore the problem from a computational perspective, utilizing first principles atomistic simulations, computational thermodynamics, plasticity theory, and morphological algorithms of image processing for defect identification. It consists of the four parts dealing with these four problem areas preceded by the introduction. In the 1st part, computational thermodynamics and ab initio calculations were used to shed light upon the different stages of zircaloy oxidation and hydrogen pickup, and microstructure optimization to increase thermal stability. The 2nd part describes the kinetic theory of oxidation of the several materials considered to be perspective coatings for Zr alloys: SiC and ZrSiO4. The 3rd part deals with understanding the respective roles of the two different plasticity mechanisms in Zr nuclear alloys: twinning (at low T) and crystallographic slip (higher T's). For that goal, an advanced plasticity model was proposed. In the 4th part projectional algorithms for defect identification in zircaloy coatings are described. Conclusions and recommendations are presented in the 5th part. This integrative approach's value is in developing multi-faceted understanding of complex processes taking place in nuclear fuel rods. It helped identify several problems pertaining to the safe operations with nuclear fuel: limits of temperature that should be strictly obeyed in storage to retard zircaloy hydriding; understanding the benefits and limitations of coatings; developing in-depth understanding of Zr plasticity; developing original algorithms for defect identification in SiC-braided zircaloy. The obtained results will be useful for the nuclear industry.
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Publisher : ASTM International
Page : 849 pages
File Size : 36,6 MB
Release :
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