Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1 PDF Author: L. J. Defferding
Publisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56

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Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1 PDF Author: L. J. Defferding
Publisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56

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The Zircaloy-2 In-pile Tube for the NRX Central Thimble

The Zircaloy-2 In-pile Tube for the NRX Central Thimble PDF Author: Richard M. Lieberman
Publisher:
ISBN:
Category : Nuclear fuel rods
Languages : en
Pages : 126

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Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the PRTR

Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the PRTR PDF Author: R. L. Knecht
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 52

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Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: R. B. Adamson
Publisher: ASTM International
ISBN: 0803109350
Category : Creep
Languages : en
Pages : 832

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Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes

Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes PDF Author: M. C. Fraser
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 26

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Stress Rupture Tests of Zircaloy-2 Pressure Tubes

Stress Rupture Tests of Zircaloy-2 Pressure Tubes PDF Author: R. C. Aungst
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 38

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Irradiation-enhanced Creep of Cold-worked Zr-2.5Nb Tubes and Helical-springs

Irradiation-enhanced Creep of Cold-worked Zr-2.5Nb Tubes and Helical-springs PDF Author: A. R. Causey
Publisher: Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories
ISBN:
Category : Anisotropy
Languages : en
Pages : 34

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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.