Effect of Corrosion and Fast Neutron Irradiation on the Mechanical Properties of the Zirconium-8.6 Wt. Per Cent Aluminum Reference Material PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Effect of Corrosion and Fast Neutron Irradiation on the Mechanical Properties of the Zirconium-8.6 Wt. Per Cent Aluminum Reference Material PDF full book. Access full book title Effect of Corrosion and Fast Neutron Irradiation on the Mechanical Properties of the Zirconium-8.6 Wt. Per Cent Aluminum Reference Material by Atomic Energy of Canada Limited. Download full books in PDF and EPUB format.
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
Get Book Here
Book Description
Author: Eugene V. T. Murphy
Publisher: Pinawa, Man. : Materials and Component Development Branch, Whiteshell Nuclear Research Establishment
ISBN:
Category :
Languages : en
Pages : 19
Get Book Here
Book Description
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author: Richard E. Schreiber
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 112
Get Book Here
Book Description
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages : 39
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1124
Get Book Here
Book Description
Author: R. S. Kemper
Publisher:
ISBN:
Category : Zirconium
Languages : en
Pages : 68
Get Book Here
Book Description
Author: Atomic Energy of Canada Limited
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
Author: E. Lijbrink
Publisher:
ISBN:
Category : Aluminum alloys
Languages : en
Pages : 14
Get Book Here
Book Description
A large number of Al 5154-0 tensile test specimens were irradiated in a core position facility of the High Flux Reactor in Petten, the Netherlands. They were withdrawn from the irradiation rig in seven batches with successively higher accumulated neutron fluences. The highest fluences achieved were 5.7 x 1026 n/m2 (E 0.414 eV) and 6.0 x 1026 n/m2 (E 0.1 MeV), which leads to a mean thermal-to-fast flux ratio of 0.95. The irradiation temperature was 360 K ± 10 K. After each withdrawal the material's tensile properties were determined at 293 K, 323 K and 373 K with a calculated strain rate ?? = 1.65 x 10-4/s. At the higher fluences the ductility figures appear to drop with increasing test temperature. Irradiation to a fluence level of 6 x 1026 n/m2 causes the 0.2% flow stress to increase from ~ 100 MPa to ~ 520 MPa and the uniform elongation to drop from more than 20% to less than 1% at the 323 K test temperature. The results of transmission electron microscopy (TEM), scanning electron microscopy (SEM) and light microscopy (LM) confirm that the behaviour of Al 5154-0 conforms to the general model for Al-Mg solid solution alloys obtained from the ORNL experiences with Al 5052-0. The objective of the irradiation program was to monitor the state of embrittlement that was expected to develop in the HFR core box material. The experimental results are representative for the PSF wall of the core box only. Because of the much higher thermal-to-fast neutron flux ratios prevailing in the other three walls, the test data are not directly applicable to these walls. By working out the implications of the basic model, however, it can be shown qualitatively that the ductility in the other walls will not be significantly better than in the PSF wall.
