Author: W. J. LangfordPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Metallurgical properties of cold-worked zircaloy-2 pressure tubes irradiated under CANDU-phw power reactor conditions
Author: W. J. LangfordMetallurgical Properties of Cold-Worked Zircaloy 2 Pressure Tubes Irradiated Under CANDU-PHW Power Reactor Conditions
Author: WJ. LangfordPublisher:
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.
Irradiation Effects on Structural Alloys for Nuclear Reactor Applications
Author: A. L. BementPublisher: ASTM International
ISBN: 9780803100695
Category : Neutron flux
Languages : en
Pages : 571
Book Description
Metallurgical Properties of Cold-worked Zircaloy-2 Pressure Tubes Irradiated for Five Years in the Npd Reactor
Author: Atomic Energy of Canada LimitedPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Nuclear Science Abstracts
Author: 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
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
Effects of Radiation on Materials
Author: Roger E. StollerPublisher: ASTM International
ISBN: 080311477X
Category : Materials
Languages : en
Pages : 1315
Book Description
Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization
Author: 
Author: