Proceedings of the Symposium on Uranium Carbides as Reactor Fuel Materials PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Proceedings of the Symposium on Uranium Carbides as Reactor Fuel Materials PDF full book. Access full book title Proceedings of the Symposium on Uranium Carbides as Reactor Fuel Materials by . Download full books in PDF and EPUB format.
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 160
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 160
Get Book Here
Book Description
Author: U.S. Atomic Energy Commission. Division of Reactor Development
Publisher:
ISBN:
Category :
Languages : en
Pages : 153
Get Book Here
Book Description
Author: Hj Matzke
Publisher: North Holland
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 352
Get Book Here
Book Description
This volume brings together 47 papers from scientists involved in the fabrication of new nuclear fuels, in basic research of nuclear materials, their application and technology as well as in computer codes and modelling of fuel behaviour. The main emphasis is on progress in the development of non-oxide fuels besides reporting advances in the more conventional oxide fuels. The two currently performed large reactor safety programmes CORA and PHEBUS-FP are described in invited lectures. The contributions review basic property measurements, as well as the present state of fuel performance modelling. The performance of today's nuclear fuel, hence UO2, at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called rim effect. Similar phenomena can be simulated by ion implantation in order to better elucidate the underlying mechanism and reviews on high resolution electron microscopy provide further information.
Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 212
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Ceramic coating
Languages : en
Pages : 518
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Ceramics
Languages : en
Pages : 84
Get Book Here
Book Description
A collection of papers is presented which ha * s the purpose of providing an introductory survey of properties involved in the choice and use of ceramic materials in nuclear technology.Topics include:Radiation fields present in nuclear reactors and the features of these fields most important to the development of nuclear materials; Principle physical effects induced in materials by reactor radiation; Solid state effects of radiation damage processes, with examples drawn partially from ceramics; Physical properties of irradiated ceramic materials; Thermodynamics of nonstoichiometry and its applications to nuclear fuels; Problems encountered in the development of nuclear fuels, reactor moderators, and structural materials.
Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 590
Get Book Here
Book Description
Author: P. Chiotti
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 772
Get Book Here
Book Description
Author: Kenneth Edwin Horton
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 540
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 320
Get Book Here
Book Description
