Author: R. L. Knecht
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 52
Book Description
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the PRTR
Author: R. L. Knecht
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Plutonium
Languages : en
Pages : 52
Book Description
Metallurgical properties of cold-worked zircaloy-2 pressure tubes irradiated under CANDU-phw power reactor conditions
Postirradiation Evaluation of Zircaloy-2 PRTR Pressure Tubes
Author: M. C. Fraser
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 26
Book Description
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 26
Book Description
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Author: L. J. Defferding
Publisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
Publisher:
ISBN:
Category : Carbon steel
Languages : en
Pages : 56
Book Description
Metallurgical Properties of Cold-worked Zircaloy-2 Pressure Tubes Irradiated for Five Years in the Npd Reactor
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes
Metallurgical Properties of Cold-Worked Zircaloy 2 Pressure Tubes Irradiated Under CANDU-PHW Power Reactor Conditions
Author: WJ. Langford
Publisher:
ISBN:
Category : Bituminous materials
Languages : en
Pages : 27
Book Description
The performance of cold-worked Zircaloy 2 reactor pressure tubes has been assessed by destructive tests of tubes irradiated under CANDU-PHW power reactor conditions of temperature (240 to 280 C), stress (10,500 to 17,200 psi), and neutron irradiation. Reactor service increases biaxial burst strength, accompanied by a change in deformation mode that leads to reduced ductility after irradiation. Crack tolerance of the tubing is virtually unaffected by reactor service, and the critical crack length exceeds 3 in. (75 mm) at 16,000 psi (11.3 kg/mm2) hoop stress and 300 C.
Publisher:
ISBN:
Category : Bituminous materials
Languages : en
Pages : 27
Book Description
The performance of cold-worked Zircaloy 2 reactor pressure tubes has been assessed by destructive tests of tubes irradiated under CANDU-PHW power reactor conditions of temperature (240 to 280 C), stress (10,500 to 17,200 psi), and neutron irradiation. Reactor service increases biaxial burst strength, accompanied by a change in deformation mode that leads to reduced ductility after irradiation. Crack tolerance of the tubing is virtually unaffected by reactor service, and the critical crack length exceeds 3 in. (75 mm) at 16,000 psi (11.3 kg/mm2) hoop stress and 300 C.
In-reactor Monitoring of Zircaloy-2 PRTR Pressure Tubes
Author: D. R. Doman
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 68
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 68
Book Description
The Physical Integrity and Corrosion Resistance of the Zircaloy-2 Pressure Tubes for the PRTR
Author: R. L. Knecht
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 86
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 86
Book Description
Interim Report on the Hydrostatic Destructive Testing of Zircaloy-2 Pressure Tubing
Author: V. E. Kahle
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 116
Book Description
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 116
Book Description