Author: W. E. Ruther
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 30
Book Description
Aqueous Corrosion of Uranium and Uranium-6 W/o Zirconium Alloy
Aqueous Corrosion of Uranium and Uranium-6 W/o Zirconium Alloy
Author: Argonne National Laboratory
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 34
Book Description
AQUEOUS CORROSION OF URANIUM AND URANIUM-6 W/o ZIRCONIUM ALLOY. Worked Performed
The High Temperature Aqueous Corrosion of Uranium Alloys Containing Minor Amounts of Niobium and Zirconium
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.
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.
High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys
Author: Stanley Kass
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 28
Book Description
Corrosion of Uranium-zirconium Alloys in Water at Temperatures Up to 100 C
Author: H. A. Pray
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 24
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 24
Book Description
The Corrosion of Low-zirconium: Uranium Alloys in Boiling Water
Author: J. E. Draley
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 60
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 60
Book Description
High-Temperature Water and Steam-Corrosion Behavior of Zirconium-Uranium Alloys
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).
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).
The Corrosion Properties of Zirconium-base Fuel Alloys
Author: Sam Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 42
Book Description
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 42
Book Description