The Development of Uranium Carbide as a Nuclear Fuel

The Development of Uranium Carbide as a Nuclear Fuel PDF Author:
Publisher:
ISBN:
Category : Uranium as fuel
Languages : en
Pages : 56

Get Book Here

Book Description

The Development of Uranium Carbide as a Nuclear Fuel

The Development of Uranium Carbide as a Nuclear Fuel PDF Author:
Publisher:
ISBN:
Category : Uranium as fuel
Languages : en
Pages : 56

Get Book Here

Book Description


The Development of Uranium Carbide as a Nuclear Fuel

The Development of Uranium Carbide as a Nuclear Fuel PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 80

Get Book Here

Book Description


The Development of Uranium Carbide as a Nuclear Fuel

The Development of Uranium Carbide as a Nuclear Fuel PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 46

Get Book Here

Book Description


Proceedings of the Symposium on Uranium Carbides as Reactor Fuel Materials

Proceedings of the Symposium on Uranium Carbides as Reactor Fuel Materials PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 160

Get Book Here

Book Description


Proceedings of the Uranium Carbide Meeting

Proceedings of the Uranium Carbide Meeting PDF Author:
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 172

Get Book Here

Book Description


Nuclear Fuel Research Fuel Cycle Development Program

Nuclear Fuel Research Fuel Cycle Development Program PDF Author: E. Gordon
Publisher:
ISBN:
Category : Metal crystals
Languages : en
Pages : 42

Get Book Here

Book Description


U Uranium

U Uranium PDF Author: H. Holleck
Publisher: Springer Science & Business Media
ISBN: 3662107163
Category : Science
Languages : en
Pages : 295

Get Book Here

Book Description
The present volume Uranium C12 covers the binary and polynary carbides of uranium, including ternary carbides with nonmetals like the carbide oxides and carbide nitrides U(C,O) and U(C,N). The binary carbide UC and especially the mixed carbide (UO.80PUO.20)C are of special importance due to their potential as the fuel for advanced .. Fast Breeder Reactors" because of properties such as the short doubling time, the high fissionable material density, and the good thermal conductivity. On the other hand, the dicarbide UC is of interest for .. High 2 Temperature Reactors", especially in the form of the mixed carbide (U . Th . )C . For O80 o20 2 the first time, India used mixed uranium-plutonium carbide (U . PU .)C as the fuel for its O3 O7 own newly developed 15 MW Fast Breeder Reactor at Kalpakkam, south of Madras. el Because of the technological importance of the uranium carbides a lot of data were published only in reports. In most cases, it was the aim of these less-scientifically based studies to promote the carbide fuel development on an economical basis. The lack of analyti cal data on the purity of the samples, missing characterization of the present phases, etc., hQINever, does not allow the discussion of the results of such references in this handbook. Therefore, only reliable publications were cited. For the technical fabrication of uranium carbides and their irradiation behavior, see Volumes A3 and A4 of this Handbook.

Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report

Nuclear Fuel Research Fuel Cycle Development Program Quarterly Progress Report PDF Author:
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 28

Get Book Here

Book Description


Progress on the Development of Uranium Carbide-type Fuels

Progress on the Development of Uranium Carbide-type Fuels PDF Author: Frank A. Rough
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 64

Get Book Here

Book Description


Nuclear Fuels and Materials Development

Nuclear Fuels and Materials Development PDF Author: William L. R. Rice
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 308

Get Book Here

Book Description