Author: L. J. DefferdingPublisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Author: L. J. DefferdingPublisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
The Zircaloy-2 In-pile Tube for the NRX Central Thimble
Author: Richard M. LiebermanPublisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 126
Book Description
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the PRTR
Author: R. L. KnechtPublisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 52
Book Description
Zirconium in the Nuclear Industry
Author: R. B. AdamsonPublisher: ASTM International
ISBN: 0803109350
Category : Creep
Languages : en
Pages : 832
Book Description
Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes
Author: M. C. FraserPublisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 26
Book Description
Stress Rupture Tests of Zircaloy-2 Pressure Tubes
Author: R. C. AungstPublisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 38
Book Description
Irradiation-enhanced Creep of Cold-worked Zr-2.5Nb Tubes and Helical-springs
Author: A. R. CauseyPublisher: Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories
ISBN:
Category : Anisotropy
Languages : en
Pages : 34
Book Description
This report investigates the anistrophy of irradiation-enhanced creep of cold-worked Zr-2.5Nb at 548-563 K using internally-pressurized capsules and axially loaded helical-springs. The test specimens were machined from small diameter extruded and cold-worked tubing that had crystallographic texture and microstructure similar to that of CANDU power reactor pressure tubes. The biaxial creep capsules and the helical-springs were irradiated for 9,525 and 16,670 hours, respectively, in a fast neutron flux.
