A proposal to irradiate zirconium alloys to determine the effect of neutron irradiation on phase transformations

A proposal to irradiate zirconium alloys to determine the effect of neutron irradiation on phase transformations PDF Author: B. A. Cheadle
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Category :
Languages : en
Pages : 0

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A proposal to irradiate zirconium alloys to determine the effect of neutron irradiation on phase transformations

A proposal to irradiate zirconium alloys to determine the effect of neutron irradiation on phase transformations PDF Author: B. A. Cheadle
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ISBN:
Category :
Languages : en
Pages : 0

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Irradiation-induced Phase Transformations in Zirconium Alloys

Irradiation-induced Phase Transformations in Zirconium Alloys PDF Author:
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Category :
Languages : en
Pages :

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[Sup 40]Ar and [sup 209]Bi ion irradiations of Zr[sub 3]Fe were performed at 35--725 K using 15-1500 keV ions. Results are presented on role of deposited-energy density on nature of the damaged regions in individual cascades produced by ion bombardment of Zr[sub 3]Fe. Comparison is also made between irradiation-induced amorphization of Zr[sub 3]Fe during electron irradiation and under ion bombardments. Dependence of damage production on incident electron energy in Zr[sub 3]Fe was also determined. Preliminary results are also discussed for amorphization of ZrFe[sub 2], Zr(Cr, Fe)[sub 2] and ZrCr[sub 2] by electron irradiation. Results of a recent investigation on amorphization of Zr(Cr, Fe)[sub 2] and Zr[sub 2](Ni, Fe) precipitates in Zircaloy-4 are discussed in context of previous experimental results of neutron and electron irradiations and likely amorphization mechanisms are proposed.

Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
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Category : Aeronautics
Languages : en
Pages : 256

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Effect of Stress on Radiation Damage in Neutron Irradiated Zirconium Alloys

Effect of Stress on Radiation Damage in Neutron Irradiated Zirconium Alloys PDF Author: CE. Coleman
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Category : Electron microscopy
Languages : en
Pages : 19

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Structures developed in zirconium alloys during irradiation creep have been characterized by transmission electron microscopy (TEM). Alloys investigated were annealed Zircaloy-2, cold-worked Zircaloy-2 and cold-worked Zr-2.5Nb pressure tube material. Thin films were taken from material deformed in the NRU, NRX and Pickering-3 reactors at temperatures of 530 to 600 K under stresses of 117 to 552 MPa giving strains in the range 0.14 to 8.8 percent. Stress-induced orientation of dislocation loops makes a negligible contribution to irradiation creep at all stresses. At the lower stresses (and hence strains), the size and distribution of the damage is unaffected by stress, being the same in the head and gage sections of creep specimens. At higher stresses (strains), there is much clearing of the damage by plastic deformation. The deformation however is very uneven, producing structures in different grains of the same specimen that can show no deformation, swaths cleared of irradiation damage, or dislocation tangles or cell formation. The relevance of these TEM observations to irradiation creep mechanisms is discussed.

Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962

Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962 PDF Author:
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Category : Zirconium alloys
Languages : en
Pages : 428

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Mechanical Properties of Irradiated Zirconium, Zircaloy, and Aluminum

Mechanical Properties of Irradiated Zirconium, Zircaloy, and Aluminum PDF Author: Richard E. Schreiber
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Category : Aluminum alloys
Languages : en
Pages : 112

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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Category : Nuclear energy
Languages : en
Pages : 1292

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Reactor Materials

Reactor Materials PDF Author:
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Category : Nuclear reactors
Languages : en
Pages : 316

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Proposal to measure the irradiation growth of various zirconium alloys and the effect of compressive stress on the growth of tubular specimens of zr-2.5 wt percent nb inside the NRX mark vi fast neutron rod

Proposal to measure the irradiation growth of various zirconium alloys and the effect of compressive stress on the growth of tubular specimens of zr-2.5 wt percent nb inside the NRX mark vi fast neutron rod PDF Author: V. Fidleris
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Category :
Languages : en
Pages : 0

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Physics Briefs

Physics Briefs PDF Author:
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Category : Physics
Languages : en
Pages : 916

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