The Effect of Fission Fragment Irradiation on the Subsequent Corrosion of Two Zirconium Alloys PDF Download
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Author: B. Cox
Publisher:
ISBN:
Category :
Languages : en
Pages : 9
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Author: B. Cox
Publisher:
ISBN:
Category :
Languages : en
Pages : 9
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Author: William C. Yee
Publisher:
ISBN:
Category : Chemical engineering
Languages : en
Pages : 108
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Author: Zefeng Yu
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Zirconium-based alloys have been used in nuclear fission reactors, because of their low thermal neutron cross-section, good mechanical strength, and adequate corrosion resistance. In pressurized water reactors, one of the major reasons that Zr-Nb alloys have widely replaced Zircaloys-4 is the absence of the accelerated oxide growth at high burnup. Although such great advantages have led to the development of many advanced commercial Zr-Nb alloys, the reasons behind the enhanced in-reactor corrosion resistance are still unclear. The distribution and concentration of alloying elements in the substrate have been suspected bo play a major role in controlling in-reactor corrosion kinetics. The major hypothesis being tested in this thesis study is that the enhanced corrosion resistance of irradiated Zr-Nb alloys is a result of irradiation-induced reduction of Nb concentration in solid solution, due to the nucleation and growth of Nb-rich irradiation-induced platelets (IIPs)/nanoclusters. To validate our hypothesis, a systematic study has been performed to understand the irradiation induced microstructure and microchemistry evolution and the subsequent effect on the corrosion kinetics of Zr-xNb (x=0.2, 0,4, 0,5, 1.0) model alloys. The microstructure and microchemistry of as-received materials were characterized under STEM/EDS/APT. Then, 2 MeV proton irradiation has been performed on these model alloys at 350 °C up to 1 dpa. (S)TEM/EDS has been used to study the size and density evolution of the native precipitate and IIPs as a function of irradiation dose. The major use of APT is to quantify the Nb concentration in the solid solution as a function of irradiation dose in order to support our hypothesis. The IIPs crystal structure and growth mechanism have been particularly inverstigated using HRSTEM and 4D-STEM. After the characterization, the irradiated materials were corroded in autoclave to study if the proton irradiation leads to subsequent lower corrosion rate. Lastly, the same characterization techniques and methods have been used to study neutron irradiated commercial alloys, M5®, ZIRLO® and X2®, in an effort to compare the results with proton irradiation. The possible IIPs nucleation and growth mechanism and the effects of irradiation-induced Nb redistribution on the corrosion kinetics are the major focuses of the discussion section.
Author: Glenn Herbert Jenks
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 50
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Author:
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ISBN:
Category :
Languages : en
Pages : 26
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Failures in the basic materials used in nuclear power plants continue to be costly and insidious, despite increasing industry vigilance to catch failures before they degrade safety. For instance, the overall costs to the US industry from materials problems could amount to as much as $10 billion annually. Moreover, estimates indicate that the cost of a pipe failure in a nuclear plant is one hundred times greater than the cost of a similar failure in a coal-fired plant. There are important practical stimuli and much scope for further understanding of the effects of irradiation on Zr-alloys (and other materials used in nuclear installations) by careful experimentation. Moreover, these studies need to address the effect of irradiation on all components of heterogeneous systems: the metal, the oxide and the environment, and especially those processes recurring at the interphases between these components. The present paper is aimed at providing specialists with some systematic information on the subject and with important considerations on the key items for further experimentation.
Author:
Publisher:
ISBN:
Category : Chemistry
Languages : en
Pages : 576
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Author: Frederic R. Shober
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
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The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 26
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Author:
Publisher:
ISBN:
Category : Corrosion and anti-corrosives
Languages : en
Pages : 156
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Author: Vladimir Markelov
Publisher:
ISBN:
Category : Metal cladding
Languages : en
Pages : 24
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In order to improve the composition and structure of zirconium alloys, it is important to know how changes in their structure-phase state under irradiation affect various properties, including corrosion. In this work, autoclave corrosion tests were carried out on fuel cladding samples made of zirconium-niobium and zirconium-niobium-tin-iron alloy systems. All samples were preliminarily irradiated in a BOR-60 nuclear reactor at a fluence of 2 x 1026 m-2 (E > 0.1 MeV). The autoclave tests of irradiated and unirradiated samples were performed at 350°C for 240 days in distilled water containing 10 ppm lithium and 1,600 ppm boron.
