Author: Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description
Evaluating Strength and Ductility of Irradiated Zircaloy, Task 5
Author: Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description
NUREG/CR.
Author: U.S. Nuclear Regulatory CommissionPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 40
Book Description
Zirconium in the Nuclear Industry
Author: Gerry D. MoanPublisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Zirconium in the Nuclear Industry: Proceedings of the Third International Conference
Author: Small Specimen Test Techniques
Author: ASTM International Committee E10 on Nuclear Technology and ApplicationsPublisher: ASTM International
ISBN: 0803128975
Category : Light water reactors
Languages : en
Pages : 495
Book Description
Irradiation Effects on the Microstructure and Properties of Metals
Author: Publisher: ASTM International
ISBN:
Category : Metals
Languages : en
Pages : 491
Book Description
Evaluating Strength and Ductility of Irradiated Zircaloy Task 5
Author: Larry M. LowryPublisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 40
Book Description
Author: 
Author: 
Author: