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Low-Temperature Aqueous Corrosion Behavior of Uranium Molybdenum Alloys

Low-Temperature Aqueous Corrosion Behavior of Uranium Molybdenum Alloys PDF Author: Levi D. Gardner
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Nuclear fuel characterization requires understanding of the various conditions to which materials are exposed in-reactor. One of these important conditions is corrosion, particularly that of fuel constituents. Therefore, corrosion behavior is of special interest and an essential part of nuclear materials characterization efforts. In support of the Office of Material Management and Minimization0́9s Reactor Conversion Program, monolithic uranium-10 wt% molybdenum alloy (UMo) is being investigated as a low enriched uranium alternative to highly enriched uranium dispersion fuel currently used in domestic high performance research reactors. The aqueous corrosion behavior of U-Mo is being examined at Pacific Northwest National Laboratory (PNNL) as part of U-Mo fuel fabrication capability activity. No prior study adequately represents this behavior given the current state of alloy composition and thermomechanical processing methods, and research reactor water chemistry. Two main measurement techniques were employed to evaluate U-Mo corrosion behavior. Low-temperature corrosion rate values were determined by means of U-Mo immersion testing and subsequent mass-loss measurements. The electrochemical behavior of each processing condition was also qualitatively examined using the techniques of corrosion potential and anodic potentiodynamic polarization. Scanning electron microscopy (SEM) and optical metallography (OM) imagery and hardness measurements provided supplemental corrosion analysis in an effort to relate material corrosion behavior to processing. The processing effects investigated as part of this were those of homogenization heat treatment (employed to mitigate the effects of coring in castings) and sub-eutectoid heat treatment, meant to represent additional steps in fabrication (such as hot isostatic pressing) performed at similar temperatures. Immersion mass loss measurements and electrochemical results both showed very little appreciable difference between specimens of different process parameters. Comparative results were presented as linear corrosion rates and temperature-dependent Arrhenius equations, which were then correlated with electrochemical and metallographic findings for each condition under investigation. This thesis was prepared in the monograph style using the ASME reference format.

Low-Temperature Aqueous Corrosion Behavior of Uranium Molybdenum Alloys

Low-Temperature Aqueous Corrosion Behavior of Uranium Molybdenum Alloys PDF Author: Levi D. Gardner
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Nuclear fuel characterization requires understanding of the various conditions to which materials are exposed in-reactor. One of these important conditions is corrosion, particularly that of fuel constituents. Therefore, corrosion behavior is of special interest and an essential part of nuclear materials characterization efforts. In support of the Office of Material Management and Minimization0́9s Reactor Conversion Program, monolithic uranium-10 wt% molybdenum alloy (UMo) is being investigated as a low enriched uranium alternative to highly enriched uranium dispersion fuel currently used in domestic high performance research reactors. The aqueous corrosion behavior of U-Mo is being examined at Pacific Northwest National Laboratory (PNNL) as part of U-Mo fuel fabrication capability activity. No prior study adequately represents this behavior given the current state of alloy composition and thermomechanical processing methods, and research reactor water chemistry. Two main measurement techniques were employed to evaluate U-Mo corrosion behavior. Low-temperature corrosion rate values were determined by means of U-Mo immersion testing and subsequent mass-loss measurements. The electrochemical behavior of each processing condition was also qualitatively examined using the techniques of corrosion potential and anodic potentiodynamic polarization. Scanning electron microscopy (SEM) and optical metallography (OM) imagery and hardness measurements provided supplemental corrosion analysis in an effort to relate material corrosion behavior to processing. The processing effects investigated as part of this were those of homogenization heat treatment (employed to mitigate the effects of coring in castings) and sub-eutectoid heat treatment, meant to represent additional steps in fabrication (such as hot isostatic pressing) performed at similar temperatures. Immersion mass loss measurements and electrochemical results both showed very little appreciable difference between specimens of different process parameters. Comparative results were presented as linear corrosion rates and temperature-dependent Arrhenius equations, which were then correlated with electrochemical and metallographic findings for each condition under investigation. This thesis was prepared in the monograph style using the ASME reference format.

The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium

The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium PDF Author: J. E. Draley
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 52

Book Description
Alloys of uranium with niobium show good corrosion resistance in degassed, distilled water to about 315 degrees C. The alloys must be quenched from the gamma phase in order to have high temperature corrosion resistance. The corrosion resistance is destroyed by over-aging at temperatures as low as 350 degrees C. Of those tried, the alloy with best resistance to thermal aging is the uranium-5% zirconium-1.5% niobium alloy. At 290 degrees C, optimum heat treatment can result in a rate of corrosion of about 6 mg/cm sq/day. Certain moderate aging treatments, e.g., 400 degree C for two hours, result in improved corrosion resistance in the initial stages of corrosion. Alloys containing 3% niobium and small amounts of tin show promise. In addition to aging, the alloys are also sensitive to hydrogen content. Ultimate corrosion failure is believed due to absorption of corrosion product hydrodgen.

Development and Properties of Uranium-base Alloys Corrosion Resistant in High Temperature Water

Development and Properties of Uranium-base Alloys Corrosion Resistant in High Temperature Water PDF Author: I. Cohen
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 322

Book Description
The effects of pile irradiations on the physical properties and corrosion resistance of U-- Mo, U-- Nb; and U--Si alloys are reported. The dimensional stability under irradiation of the gamma phase U-- Mo and U-- Nb alloys is excellent; however, an isotropic volume increase of 4 to 6% per wt.% burnup may limit the ultimate fuel element life. Corrosion resistance of the gamma-phase alloys appesrs to be improved when subjected to s neutron field; this is attributed to an irrsdiation induced stabilization of the gamma phases. The U/ sub 3/Si alloy, on the other hand, suffered severe deterioration, particularly of corrosion resistance. Changes in electrical resistivity, hardness, mechanical properties, and crystal structure are presented and the mechanisms producing the observed changes discussed.

Resume of Uranium Alloy Data

Resume of Uranium Alloy Data PDF Author: E. F. Losco
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 116

Book Description


The Corrosion Properties of Zirconium-base Fuel Alloys

The Corrosion Properties of Zirconium-base Fuel Alloys PDF Author: Sam Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 42

Book Description


Resume of Uranium Alloy Data

Resume of Uranium Alloy Data PDF Author: D. E. Thomas
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 38

Book Description


Corrosion-resistant Uranium Alloys

Corrosion-resistant Uranium Alloys PDF Author: R. K. McGeary
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 58

Book Description


High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys

High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys PDF Author: Stanley Kass
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 28

Book Description


AEC-Euratom Conference on Aqueous Corrosion of Reactor Materials

AEC-Euratom Conference on Aqueous Corrosion of Reactor Materials PDF Author:
Publisher:
ISBN:
Category : Corrosion and anti-corrosives
Languages : en
Pages : 474

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 808

Book Description