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Preliminary Irradiations of the Ceramic Fuels UO2, UO2-Zr, and ThO2-UO2

Preliminary Irradiations of the Ceramic Fuels UO2, UO2-Zr, and ThO2-UO2 PDF Author: J. H. Kittel
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 36

Book Description


Preliminary Irradiations of the Ceramic Fuels UO2, UO2-Zr, and ThO2-UO2

Preliminary Irradiations of the Ceramic Fuels UO2, UO2-Zr, and ThO2-UO2 PDF Author: J. H. Kittel
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 36

Book Description


Information Circular

Information Circular PDF Author:
Publisher:
ISBN:
Category : Mine safety
Languages : en
Pages : 724

Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1148

Book Description


Symposium on Effects of Irradiation on Fuel and Fuel Elements

Symposium on Effects of Irradiation on Fuel and Fuel Elements PDF Author: W. D. Manly
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 114

Book Description


TID.

TID. PDF Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 312

Book Description


Helium

Helium PDF Author: Carla W. Cherry
Publisher:
ISBN:
Category : Alpha rays
Languages : en
Pages : 536

Book Description


Thorium Fuel Cycle

Thorium Fuel Cycle PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 120

Book Description
Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.

List

List PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 564

Book Description


Irradiation of Metal-fiber-reinforced Thoria-urania

Irradiation of Metal-fiber-reinforced Thoria-urania PDF Author: L. A. Neimark
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 56

Book Description
Fission gas release from unclad fibered pellets was a maximum of 15.3% of theoretical at a burnup of 31,500 Mwd/T (8.3 x l0/0 fiss/cc) and an integral kd theta value of 57 w/cm. Gas release from similarly irradiated un-fibered pellets was a maximum of 6.3% at 21,800 Mwd/T 16.6 x 10/0 fiss/cc) and an integral kd theta value of 92 w/ cm. The disparity in gas release is attributed to the breaking into pieces of the un-fibered pellets early in the irradiation and their consequent operation at significantly lower temperatures than the fibered pellets.

Proceedings of Technical Meetings

Proceedings of Technical Meetings PDF Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 36

Book Description