Irradiation Creep and growth of annealed zircaloy 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 Irradiation Creep and growth of annealed zircaloy PDF full book. Access full book title Irradiation Creep and growth of annealed zircaloy by R. A. Holt. Download full books in PDF and EPUB format.
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
Get Book Here
Book Description
Author: OJV Chapman
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 32
Get Book Here
Book Description
Proton irradiation creep and in-pile creep and growth tests have been conducted on specimens cut from the same rolled and annealed Zircaloy-2 plate. The proton irradiation creep tests were carried out over the following ranges: stress, 0 to 267 MPa; damage rate, 0.15 to 7.0 x 10-7 dpa/s; temperature, 513 to 613 K; and dose, up to 1.44 dpa.
Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
Get Book Here
Book Description
Author: A. R. Causey
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the full-length high temperature experiment-5 (flht-5) to be conducted in the l-24 position of the national research universal (nru) reactor at chalk river nuclear laboratories (crnl), ontario, canada. the test is sponsored by an international group organized by the u.s. nuclear regulatory commission. the test is designed and conducted by staff from pacific northwest laboratory with crnl staff support. the test will study the consequences of loss-of-coolant and the progression of severe fuel damage. an array of full-length lwr fuel rods will be subjected to conditions that simulate loss-of-coolant flow at decay-heat power level. the 12-position array includes one pre-irradiated pwr rod, 10 fresh fuel rods, and one instrument thimble containing a dummy steel rod. the boilaway of the coolant will permit heatup of the rods to the point of rapid cladding oxidation with concomitant cladding melting, partial fuel liquefaction, fuel oxidation, hydrogen generation, and fission product release. the hydrogen generation (from the oxidation reaction), the bundle temperatures, the liquid level, and the fission product release will be monitored during the test. the melt progression will be assessed using post test visual and metallographic examination results. experience from similar flht tests is combined with analysis results to show that: 1) high-temperature material will be contained within the shroud that surrounds the rod array, precluding damage to the nru loop pressure tube; 2) the released fission products and hydrogen will be contained and disposed of by the effluent control system in a manner that poses no unresolved safety hazard to operating personnel or to the public; and 3) the radiation exposure to operating personnel and to the public will remain below approved control limits.
Author: J. Walter Joseph
Publisher:
ISBN:
Category : Stress relaxation (Physics)
Languages : en
Pages : 28
Get Book Here
Book Description
Author: JY. Ren
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 8
Get Book Here
Book Description
Experimental investigation of irradiation growth on annealed Zircaloy-4 and 20% to 50% cold-worked Zr-2.5wt%Nb specimens with stress relief has been carried out. The specimens are irradiated in a heavy water reactor at 610 K to 4.2 x 1024 n/m2 (E > 1.0 MeV). The growth strains increase linearly with fluence. The saturation of growth is not observed for all specimens. The difference of growth behavior between two kinds of Zircaloy-4 tube may be associated with the content of minor alloying elements and impurities that influence the microstructure evolution under irradiation.
Author: A. R. Causey
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Get Book Here
Book Description
The possibility of accelerating creep at low temperature in annealed zircaloy at high fluences, similar to previously reported growth 'breakaway' behaviour at temperatures above 500 k, has been investigated at 340 k using stress relaxation and irradiation growth tests on annealed zircaloy-4 pre-irradiated at 580 k to 5 x 10sup(24) and 8 x 10sup(25) n.m-2 e1 mev. test results suggest that both creep and growth rates are higher for the specimens pre-irradiated to the higher fluence, however, the stress relaxation data are not conclusive. the presence of c component dislocations, revealed by transmission electron microscopy, only in the high fluence material has been related previously to the growth 'breakaway' at 580 k, and appears to result in higher growth and creep rates at 340 k.
Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Get Book Here
Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
