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

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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


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


High-Temperature Water and Steam-Corrosion Behavior of Zirconium-Uranium Alloys

High-Temperature Water and Steam-Corrosion Behavior of Zirconium-Uranium Alloys PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
Weight change vs. time curves expressing the corrosion behavior of zirconium alloys containing additions of 10 through 60 wt.% uranium tested in 600 and 680 F water and in 750 F steam at 1500 psi are presented. The effects of various heat treatments on the subsequent corrosion properties are also included. (auth).

Compositional Factors Affecting Corrosion Resistance of Zirconium in High-temperature Water and Steam

Compositional Factors Affecting Corrosion Resistance of Zirconium in High-temperature Water and Steam PDF Author: Walter K. Boyd
Publisher:
ISBN:
Category : Corrosion and anti-corrosives
Languages : en
Pages : 100

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


Corrosion of Zirconium Alloys in 900 and 1000° Steam

Corrosion of Zirconium Alloys in 900 and 1000° Steam PDF Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 28

Book Description


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.

The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water

The Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water PDF Author: Stanley Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 34

Book Description


The Corrosion of Low-zirconium

The Corrosion of Low-zirconium PDF Author: J. E. Draley
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 56

Book Description
The corrosion behavior of uranium alloys containing up to about 6 weight percent zirconium has been studied in boiling distilled water. Alloys containing on the order of 5 or 6 weight percent zirconium form good protective oxide films under certain conditions. So long as the protective film covers the metal surface, corrosion rates less than one-thousandth that of uranium are characteristically obtained. The degree of permanence of such films has not been determined, although the film on one sample was observed to be still protective after three months exposure. Protective films are formed at temperatures at least as high as 155C.

Corrosion of Zirconium Alloys in 900° Steam

Corrosion of Zirconium Alloys in 900° Steam PDF Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 26

Book Description


Research on the Corrosion of Zirconium Alloys in Water and Steam at High Temperature and Pressure

Research on the Corrosion of Zirconium Alloys in Water and Steam at High Temperature and Pressure PDF Author: A. A. Kiselev
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 48

Book Description