Author: C. W. Loveland
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 54
Book Description
Production of Molybdenum-uranium and Zirconium-uranium Alloys
Author: C. W. Loveland
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 54
Book Description
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 54
Book Description
Some Properties of Uranium-molybdenum Alloy Fuels for Organic Moderated Reactors
Author: W. H. Friske
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 30
Book Description
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 30
Book Description
The Determination of Zirconium, Molybdenum, and Niobium in Two Samples of Uranium Alloy
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 1
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 1
Book Description
Processing of Uranium-zirconium Alloys
Author:
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 20
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 20
Book Description
Resume of Uranium Alloy Data
Author: D. E. Thomas
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 38
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 38
Book Description
Uranium Alloys for High-temperature Application
Author: Henry A. Saller
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 46
Book Description
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 46
Book Description
ALLOYS OF URANIUM WITH ZIRCONIUM, CHROMIUM, COLUMBIUM VANADIUM, AND MOLYBDENUM.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Irradiation of U-Mo Base Alloys
Author: M. P. Johnson
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 38
Book Description
A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
Publisher:
ISBN:
Category : Molybdenum alloys
Languages : en
Pages : 38
Book Description
A series of experiments was designed to assess the suitability of uranium-molybdenum alloys as high-temperature, high-burnup fuels for advanced sodium cooled reactors. Specimens with molybdenum contents between 3 and 10% were subjected to capsule irradiation tests in the Materials Testing Reactor, to burnups up to 10,000 Mwd/MTU at temperatures between 800 and 1500 deg F. The results indicated that molybdenum has a considerable effect in reducing the swelling due to irradiation. For example. 3% molybdemum reduces the swelling from 25%, for pure uranium. to 7% at approximates 3,000 Mwd/MTU at 1270 deg F. Further swelling resistance can be gained by increasing the molybdenum content, but the amount gained becomes successively smaller. At higher irradiation levels, the amount of swelling rapidly becomes greater, and larger amounts of molybdenum are required to provide similar resistance. A limit of 7% swelling, at 900 deg F and an irradiation of 7,230 Mwd/ MTU, requires the use of 10% Nonemolybdenum in the alloy. The burnup rates were in the range of 2.0 to 4.0 x 10p13s fissiom/cc-sec. Small ternary additions of silicon and aluminum were shown to have a noticeable effect in reducing swelling when added to a U-3% Mo alloy base. Under the conditions of the present experiment, 0.26% silicon or 0.38% aluminum were equivalent to 1 to 1 1/2% molybdenum. The Advanced Sodium Cooled Reactor requires a fuel capable of being irradiated to 20,000 Mwd/MTU at temperatures up to 1500 deg C in metal fuel, or equivalent in ceramic fuel. It is concluded that even the highest molybdenum contents considered did not produce a fuel capable of operating satisfactorily under these conditions. The alloys would be useful, however, for less exacting conditions. The U-3% Mo alloy is capable of use up to 3,000 Mwd/MTU at temperatures of 1300 deg F before swelling becomes excessive. The addition of silicon and aluminum would increase this limit to at least 3,000 Mwd/MTU, and possibly more if the
Uranium Processing and Properties
Author: Jonathan S. Morrell
Publisher: Springer Science & Business Media
ISBN: 1461475910
Category : Technology & Engineering
Languages : en
Pages : 320
Book Description
Uranium Processing and Properties describes developments in uranium science, engineering and processing and covers a broad spectrum of topics and applications in which these technologies are harnessed. This book offers the most up-to-date knowledge on emerging nuclear technologies and applications while also covering new and established practices for working with uranium supplies. The book also aims to provide insights into current research and processing technology developments in order to stimulate and motivate innovation among readers. Topics covered include casting technology, plate and sheet rolling, machining of uranium and uranium alloys, forming and fabrication techniques, corrosion kinetics, nondestructive evaluation and thermal modeling.
Publisher: Springer Science & Business Media
ISBN: 1461475910
Category : Technology & Engineering
Languages : en
Pages : 320
Book Description
Uranium Processing and Properties describes developments in uranium science, engineering and processing and covers a broad spectrum of topics and applications in which these technologies are harnessed. This book offers the most up-to-date knowledge on emerging nuclear technologies and applications while also covering new and established practices for working with uranium supplies. The book also aims to provide insights into current research and processing technology developments in order to stimulate and motivate innovation among readers. Topics covered include casting technology, plate and sheet rolling, machining of uranium and uranium alloys, forming and fabrication techniques, corrosion kinetics, nondestructive evaluation and thermal modeling.
Uranium Alloy Development Program for OMR
Author: W. H. Friske
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 56
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 56
Book Description